CN102696073B

CN102696073B - The method and system of fuel assembly is migrated in fission-type reactor

Info

Publication number: CN102696073B
Application number: CN201080060896.2A
Authority: CN
Inventors: E.格林斯潘; R.A.海德; R.C.佩特罗斯基; J.C.沃尔特; T.A.威佛; C.惠特默; 小劳威尔.L.伍德; G.B.齐默尔曼
Original assignee: TerraPower LLC
Current assignee: TerraPower LLC
Priority date: 2009-11-06
Filing date: 2010-11-05
Publication date: 2018-05-18
Anticipated expiration: 2030-11-05
Also published as: EA024235B1; JP2013510313A; KR20120093325A; JP2016048268A; WO2011093845A2; KR20120083507A; CN102714067B; WO2011093845A3; JP2013510309A; CN102714066A; JP6255426B2; RU2012120918A; BR112012010797A2; WO2011093841A3; WO2011056235A1; JP6166535B2; RU2557563C9; EP2497088A4; RU2012120915A; JP2013510314A

Abstract

Exemplary embodiments provide the nuclear fission traveling wave reactor of the method and system that fuel assembly is migrated in fission-type reactor, the method for operating nuclear fission traveling wave reactor, the method for controlling nuclear fission traveling wave reactor, the system for controlling nuclear fission traveling wave reactor, the computer software program product for controlling nuclear fission traveling wave reactor and the system with migration fuel assembly.

Description

The method and system of fuel assembly is migrated in fission-type reactor

Technical field

The present invention relates to the method and systems that fuel assembly is migrated in fission-type reactor.

Background technology

Cross

This application involves applications listed below（" related application "）And requirement is obtained from application listed below and earliest may be used With the rights and interests of live application day（Such as, it is desirable that the priority date available earliest of non-provisional requires SProvisional Patent Shen Please and any and all parent of related application, Zu Fudai, great grandfather generation etc. applications be based on 35USC § 119（e）Rights and interests）. All themes of the applications such as any and all parent of related application and related application, Zu Fudai, great grandfather's generation are with such Theme will not be inconsistent with the theme of this paper degree be herein incorporated by reference.

Related application

For U.S.Patent ＆ Trademark Office（USPTO）Non- legal requirements, the application form on November 6th, 2009 submit, hair A person of good sense is Ehud Greenspan, Roderick A.Hyde, Robert C.Petroski, Joshua C.Walter, Thomas Allan Weaver, Charles Whitmer, Lowell L.Wood, Jr. and George B.Zimmerman, denomination of invention For " METHODS AND SYSTEMS FOR MIGRATING FUEL ASSEMBLIES IN A NUCLEAR FISSION REACTOR（The method and system of fuel assembly is migrated in fission-type reactor）" U.S. Patent Application No. 12/590,448 Number part continuation application, this application is currently co-pending or gives current co-pending application with the rights and interests of the applying date Application.

For U.S.Patent ＆ Trademark Office（USPTO）Non- legal requirements, the application form on January 25th, 2010 submit, hair A person of good sense is Ehud Greenspan, RoderickA.Hyde, Robert C.Petroski, Joshua C.Walter, Thomas Allan Weaver, Charles Whitmer, Lowell L.Wood, Jr. and George B.Zimmerman, denomination of invention For " METHODS AND SYSTEMS FOR MIGRATING FUEL ASSEMBLIES IN A NUCLEAR FISSION REACTOR（The method and system of fuel assembly is migrated in fission-type reactor）" U.S. Patent Application No. 12/657,725 Number part continuation application, this application is currently co-pending or gives current co-pending application with the rights and interests of the applying date Application.

For U.S.Patent ＆ Trademark Office（USPTO）Non- legal requirements, the application form on January 25th, 2010 submit, hair A person of good sense is Ehud Greenspan, RoderickA.Hyde, Robert C.Petroski, Joshua C.Walter, Thomas Allan Weaver, Charles Whitmer, Lowell L.Wood, Jr. and George B.Zimmerman, denomination of invention For " METHODS AND SYSTEMS FOR MIGRATING FUEL ASSEMBLIES IN A NUCLEAR FISSION REACTOR（The method and system of fuel assembly is migrated in fission-type reactor）" U.S. Patent Application No. 12/657,726 Number part continuation application, this application is currently co-pending or gives current co-pending application with the rights and interests of the applying date Application.

For U.S.Patent ＆ Trademark Office（USPTO）Non- legal requirements, the application form on January 25th, 2010 submit, hair A person of good sense is Ehud Greenspan, RoderickA.Hyde, Robert C.Petroski, Joshua C.Walter, Thomas Allan Weaver, Charles Whitmer, Lowell L.Wood, Jr. and George B.Zimmerman, denomination of invention For " METHODS AND SYSTEMS FOR MIGRATING FUEL ASSEMBLIES IN A NUCLEAR FISSION REACTOR（The method and system of fuel assembly is migrated in fission-type reactor）" U.S. Patent Application No. 12/657,735 Number part continuation application, this application is currently co-pending or gives current co-pending application with the rights and interests of the applying date Application.

U.S.Patent ＆ Trademark Office（USPTO）The computer program requirement patent applicant of the issued USPTO that come into force draws With sequence number and instruction application whether be parent application continuation application, the bulletin of part continuation application or divisional application.Have inside the Pass Appearance refers to Stephen G.Kunin, Benefit of Prior-Filed Application, USPTO Official Gazette March 18,2003.The applicant's entity（Hereinafter referred to as " applicant "）It is being provided above such as regulation institute State the specific reference for the application for requiring its priority.The applicant understands, the regulation be in its specific specific quote language it is specific, Sequence number or any characterization as " continuation " or " continuing part " is not required to carry out the priority of requirement U.S. Patent application.To the greatest extent It manages as described above, but the applicant understands, and the computer program of USPTO has some data entry requirements, therefore the applicant Specifying for the relation between the application as described above and its parent application is provided, but should be understood that and point out, it is such to specify never It is understood that into addition to the theme of its parent application, whether any types comprising certain new theme are annotated and/or held the application Recognize.

The content of the invention

Exemplary embodiments provide the method and system that fuel assembly is migrated in fission-type reactor, operation nuclear fission The method of traveling wave reactor, the method for controlling nuclear fission traveling wave reactor, the system for controlling nuclear fission traveling wave reactor, control core The computer software program product of fission traveling wave reactor and the nuclear fission traveling wave reaction with the system for migrating fuel assembly Heap.

What summary above was merely an illustrative, and be never intended to limit the invention in any way.Except above-mentioned Outside illustrative aspect, embodiment and feature, by reference to attached drawing and detailed further below, further aspect will be made, implemented Example and feature become apparent.

Description of the drawings

Figure 1A is the block diagram for the exemplary methods for operating nuclear fission traveling wave reactor；

Figure 1B -1D are the perspective views of the partially schematic form of the component of illustrative fission-type reactor reactor core；

Fig. 1 E-1H instantiate the shadow of the migration of selected fission fuel subassembly to the shape of nuclear fission traveling wave burnfront It rings；

Fig. 1 I are the block diagrams of the details of the part of the method for Figure 1A；

Fig. 1 J instantiate the rotation of fission fuel subassembly；

Fig. 1 K are the block diagrams of the details of the part of the method for Figure 1A；

Fig. 1 L instantiate the reverse of fission fuel subassembly；

Fig. 1 M-1N are the block diagrams of the details of the part of the method for Figure 1A；

Fig. 1 O instantiate the spiral migration of fission fuel subassembly；

Fig. 1 P are the block diagrams of the details of the part of the method for Figure 1A；

Fig. 1 Q instantiate the axial migration of fission fuel subassembly；

Fig. 1 R instantiate the approximately spherical of nuclear fission traveling wave burnfront；

Fig. 1 S instantiate the continuous bend surface of nuclear fission traveling wave burnfront；

Fig. 1 T instantiate the substantially non-rotational symmetric shape of nuclear fission traveling wave burnfront；

Fig. 1 U-1V instantiate the substantially n fold rotational symmetry of the shape of nuclear fission traveling wave burnfront；

Fig. 1 W instantiate the asymmetrical shape of nuclear fission traveling wave burnfront；

Fig. 1 X-1AF are the block diagrams of the details of the part of the method for Figure 1A；

Fig. 2A is the block diagram for the exemplary methods for controlling nuclear fission traveling wave reactor；

Fig. 2 B-2M are the block diagrams of the details of the part of the method for Fig. 2A；

Fig. 3 A are to determine the block diagram of the illustrative system of the migration of fission fuel subassembly；

Fig. 3 B-3C are the block diagrams of the details of the component of the system of Fig. 3 A；

Fig. 4 A are the block diagrams for the illustrative system for migrating fission fuel subassembly；

Fig. 4 B-4C are the block diagrams of the details of the component of the system of Fig. 4 A；

Fig. 5 is the block diagram of the partially schematic form of illustrative nuclear fission traveling wave reactor；

Fig. 6 A are the flow charts for the exemplary methods for operating nuclear fission traveling wave reactor；

Fig. 6 B are the block diagrams of the details of the part of the method for Fig. 6 A；

Fig. 7 is the flow chart for the exemplary methods for operating nuclear fission traveling wave reactor；

Fig. 8 is the flow chart for the exemplary methods for operating nuclear fission traveling wave reactor；

Fig. 9 is the flow chart for the exemplary methods for operating nuclear fission traveling wave reactor；

Figure 10 A are the flow charts for the exemplary methods for operating nuclear fission traveling wave reactor；

Figure 10 B-10D are the block diagrams of the details of the part of the method for Figure 10 A；

Specific embodiment

In the following detailed description, with reference to the attached drawing for forming its part.In the accompanying drawings, similarity sign usually identifies similar portion Part, unless otherwise indicated by context.Exemplary embodiments in detailed description, attached drawing and claims and unawareness are described Taste restricted.Can without departing from the theme shown here spirit or scope using other embodiments and can making Go out other changes.

Nuclear fission traveling wave is summarized

Before the details in relation to non-limiting example given herein is illustrated, the letter in relation to nuclear fission traveling wave will be provided It summarizes.Although nuclear fission traveling wave is also referred to as nuclear fission deflagration wave, for clarity, nuclear fission traveling wave is referred to herein. Some parts as discussed below include the information taken passages from following paper：Entitled " Completely Automated Nuclear Power Reactors For Long-Term Operation:III.Enabling Technology For Large-Scale, Low-Risk, Affordable Nuclear Electricity ", author for Edward Teller, Muriel Ishikawa, Lowell Wood, Roderick Hyde and John Nuckolls, are presented in July, 2003 Workshop of the Aspen Global Change Institute,University of California Lawrence Livermore National Laboratory publication UCRL-JRNL-122708(2003)（This Piece paper preparation is submitted toEnergy, The International Journal,30 November 2003）, hereby by drawing With being incorporated to its content.

In " ripple " for the reactor core for moving past nuclear fission traveling wave reactor with the speed of about one centimetre or so the order of magnitude every year, Convertible fission fuel regenerates fissionable nucleus fission fuel, then the fission of fissionable nucleus fission fuel experience.

For be used in some fission fuels imagined in nuclear fission traveling wave reactor without limitation as（Naturally, dilution, Or concentration）Uranium, thorium, plutonium or even former burned fission fuel assemblies were such, usually broadly available.It can also use Other less widely available fission fuels without limitation as other actinides or its isotope.Some cores are split Become traveling wave reactor with the intending full power order of magnitude of or so or so 1/3rd century of longtime running to 1/2nd century or longer time.One A little nuclear fission traveling wave reactors are not intended to change nuclear fuel（And emergency burial when being intended to life knot phase beam）, but some other cores Nuclear fuel-some are changed during nuclear fuel is happened at shutdown and some change nuclear fuel and are happened at band is changed in fission traveling wave reactor plan During Power operation.It is also intended to reprocess to avoid fission fuel in some cases, so as to reduce steering military use With the possibility of other problems.

Realize with not changing nuclear fuel Operation at full power 1/3-1/2 centuries（Or the longer time）And avoid fission fuel again Compatible hope allows to need to use fast neutron spectrum while processing.In addition, the propagation of nuclear fission traveling wave allows to reach picture The high average burn-up of non-concentrated actinium series fuel as natural uranium or thorium and in the loading area of reactor core use fissionable nucleus material Appropriate isotopic enrichment smaller " nuclear fission igniter " region.

In this way, nuclear fission traveling wave reactor core can suitably include nuclear fission igniter and larger nuclear fission detonation is fired Burn wave propagation area.Nuclear fission detonation burning wave propagation area is suitably comprising thorium or uranium fuel, and fissioned according to fast neutron spectrum The General Principle of multiplication works.

Requirement for the utilization of effective fission fuel and to enriched isotope is minimum, makes nuclear fission traveling wave reactor core It is appropriate multiplier (-icator).Also, suitably using fast neutron spectrum, because not removing fission product, big suction of the fission product to thermal neutron Receiving section usually makes thorium or in uranium fuel embodiment, more rich uranium isotope²³⁸The fuel of U is not fully utilized.

It will now describe illustrative nuclear fission traveling wave.Detonation combustion wave can be discharged by the propagation of fission fuel can be pre- The flat power of water breakthrough.In addition, if as the configuration found in typical commercial power generation nuclear reactor, material configuration tool There are sufficient time invariant features, then thing followed power generation may be on maintenance level.It finally, if can be with practicality Mode adjusts traveling wave spread speed from outside, then energy release rate can be controlled as desirable, therefore controls power production It is raw.

Illustrate the nucleonics of nuclear fission traveling wave below.The neutron for absorbing any energy induces actinides-fissionable element The nuclear fission of selected isotope may to discharge nuclear-binding energy in any material temperature including arbitrary low temperature.It is fissible The neutron that actinides absorbs can be provided by nuclear fission igniter.

The nuclear fission of substantially any actinium series isotope often absorbs each neutron release more than one neutron, Ke Yi to average The chance of diverging neutron mediation nuclear fission chain reaction is provided in such material.In general, the neutron population by each absorption release It is expressed as η, wherein η=υ σ_f/(σ_f+σ_c), υ is the neutron population of each fission release.The each neutron absorbed（On average, at certain In a neutron energy scope）Release more than two neutron may be such that the atom of not fissionable isotope is captureed by primary neutron first It obtains and is converted into fissionable isotope（It decays via neutron absorption and subsequent β）, then, in addition make newly to generate fissionable isotope During second of neutron fission absorbs neutron fission occurs for atomic nucleus.

If on average, a neutron from given nuclear fission event can be in not fissible but " convertible " atom It is then converted on core by radiation capture, not fissible but " convertible " atomic nucleus（As via β decays）Being converted into can Fission atom core and second neutron from identical fission event can be captured on fissionable atom core, so as to lure Shattered crack becomes, then can be by most of high Z（Z≥90）Nucleic is used as traveling wave reactor（Or breeder reactor）In fission fuel Material.In particular, if these any one arranged are all stable states, it can meet and propagate nuclear fission in given material The adequate condition of traveling wave.

Since the β that convertible consideration convey is changed into isotope among during fissionable nucleus decays, fissioner is enable to be used It is restricted in the ratio of fission.Therefore, wavefront into characteristic velocity limited by the half-life period of several days or order of magnitude some months.Example Such as, wavefront into characteristic velocity can such ratio the order of magnitude, neutron is born to it from its fission on convertible core The distance advanced of radiation capture（That is, mean free path）β with becoming fissionable nucleus from convertible core decays（In chain most Long-life atomic nucleus）Half-life period ratio.It is such in normal density actinium series for interested majority of case Feature fission neutron transport distance approximation 10cm and β decay half-life period are 10⁵-10⁶Second.Then, designed for some, characteristic wave Speed is 10^-4-10^-7cm/s.Such opposite speed that is advanced slowly shows to levy wave table into traveling wave（traveling wave）Or deflagration wave（deflagration wave）Rather than detonation wave（detonation wave）.

If traveling wave attempts to accelerate, its forward position can run into even more pure fertile material（In the sense that neutron For, loss is relatively large）, because the concentration exponentially of the fissionable nucleus before ripple center declines.Therefore, the forward position of ripple （Hereinafter referred to as " burnfront "）It is slow or slow.On the contrary, if ripple is slow, and conversion ratio is remained above 1（Namely It says, proliferation rate is more than fission rate）, then the local concentration increase of the fissionable nucleus as caused by decaying continuous β.Fission and generation neutron Local velocity rise and ripple forward position, i.e. burnfront accelerate.

Finally, if sufficiently rapidly from ripple propagate initial convertible substance configuration all parts in remove and core It fissions associated heat, although-the temperature of both neutron and fissioning nucleus can be happened in arbitrarily low material temperature by then propagating Can be about 1MeV（Million electro-volt）.

The condition for so triggering and propagating nuclear fission traveling wave can be realized using that can be readily available material.Although actinium series is first The fissionable isotope of element is rare on land for the fertile isotope of these elements with regard to absolute and relative, but It can concentrate, concentrate and synthesize fissionable isotope.For example, use picture respectively in initial fission chain reaction²³³U、²³⁵U With²³⁹Natural and artificial fissionable isotope is well-known as Pu.

The considerations of related neutron cross section, implies, if the neutron spectra in ripple is " hard " or " fast " neutron spectra, nuclear fission row Ripple can burn picture²³²Th or²³⁸The significant portion of the reactor core of natural actinides as U.If that is, in ripple It is not very little compared with the neutron of progress chain reaction has the approximate 1MeV being evaporated with them from newborn fission fragment Energy, then, when the local quality share of fission product and the suitable local quality share of fertile material（Recall one Mole fissile material fission be converted into two moles of fission-product nucleus）, can be to avoid the opposite of local space time's neutron economy Greater loss.Neutron loss even with desired hot properties, the typical neutron reactor structural material as Ta exists The neutron energy of≤0.1MeV also becomes quite big.

Another kind consider be with the fission of incident neutron energy neutron multiplication rate v and cause to fission（Rather than just in Gamma-rays caused by muon capture emits）All neutron-absorbing events share α（It is relatively small）Variation.Function alpha (v-2) Algebraic symbol forms each fissionable isotope for reactor core, is posted in vivo not from reactor core leakage neutron or at it It is raw to absorb（As on fission product）In the case of, with total comparable fertile material of fissionable isotope mass budget The condition of the middle feasibility for propagating nuclear fission traveling wave.It can drop to resonance capture region for the fission neutron from approximate 1MeV All fissionable isotopes interested, the algebraic symbol are typically all positive.

Amount alpha (v-2)/v is that total fission generation neutron may be because of leakage, parasitic absorption, geometry hair between traveling wave propagation periods The upper limit for the share for dissipating and losing.Note that match somebody with somebody for generally appearing in actual interested all effectively non-slowing down actinides Neutron energy scope in putting（Approximate 0.1-1.5MeV）On most of fissionable isotopes, this share is 0.15-0.30. With for（It is super）The situation of generally existing is on the contrary, parasitic loss ratio can wherein as caused by fission product for the neutron of thermal energy Those high 1-1.5 decimal number magnitudes of loss of fissible conversion are transformed into, it can on neutron energy scope 0.1-1.5MeV The fissionable element generation for converting isotope capture captures the excellent 0.7-1.5 order of magnitude than fission product.The former, which implies, is hankering Can be switched on or near sub- energy fissible conversion only can reach 1.5-5% degree it is feasible, and the latter represent, near Disintegration energy neutron spectra, it is contemplated that the conversion more than 50%.

When considering to propagate the condition of nuclear fission traveling wave, in some means, match somebody with somebody for very big, " self-reflection " actinides It puts, neutron leakage can be effectively marginalized out.It will be understood that, two kinds of actinides of relative abundance on land can be distinguished：²³²Th With²³⁸The uniqueness of U-natural thorium and uranium and main（MaLS）Traveling wave propagation is established in the sufficiently large configuration of isotopic composition.

Specifically, fission neutron transporting in these actinium series isotopes is likely to result in being remarkably decreased in neutron energy To below 0.1MeV（It is easily captured therewith with non-inappreciable possibility on fission-product nucleus）Before, in fertile isotope The fission of capture or fissionable isotope core on core.It will be understood that, fission product nuclear concentration can approach or in some cases More than convertible nuclear concentration, and fissionable nucleus concentration is while keeping quantity quite reliable, can be than fission product or can Convert the small order of magnitude of the smaller of core.The considerations of related neutron scattering section, implies, fully prolongs in their radial dimension Stretch so that for fission neutron with effective infinite thickness-that is, the configuration of the actinides of self-reflection will be with >>200gm/cm²（Gram per centimeter²）Density-radius product-that is, they will have²³⁸U-²³²Th density of solid>> The radius of 10-20cm.

Multiplication and combustion wave provide fully superfluous neutron, go out to become unburned in 1-2 mean free path internal breeding to combust The new fissile material of material, is effectively substituted in fissionable fuel burned in ripple." lime-ash " behind burning crest is substantially It is " neutron is neutral ", because the neutron reaction of its fission fraction is just by splitting at the top of the parasitic absorption of structure and leakage Become product storage balance.It is time static state that if ripple center and fissionable atom storage just in front of it are propagated with ripple , then it can be steadily in this way, if it is less, ripple " dead "；And if it does, it may be considered that ripple " plus Speed ".

Therefore, it can propagate and protect under basic limit with long interval of time in the configuration of natural actinium series isotope Hold nuclear fission traveling wave.

Above discussion considers the circle of natural uranium of the diameter less than one meter or so or thorium metal by non-limitative example If cylinder using effective neutron reflector that nuclear fission traveling wave can be made to stablize the arbitrarily long axial distance of propagation, can make Diameter is much smaller.But the propagation of nuclear fission traveling wave should not be construed as limited to cylinder, symmetrical geometry or simply connected are several What.For this purpose, the additional embodiment of the alternative geometry of nuclear fission traveling wave reactor core has been described in the following literature it：2006 Submission on November 28, inventor RODERICK A.HYDE, MURIEL Y.ISHIKAWA, NATHAN P.MYHRVOLD and LOWELL L.WOOD, JR., entitled " AUTOMATED NUCLEAR POWER REACTOR FOR LONG-TERM The U.S. Patent Application No. of OPERATION " 11/605,943, is incorporated by reference into its content hereby.

The propagation of nuclear fission traveling wave has Suggestion to the embodiment of nuclear fission traveling wave reactor.It, can as first example With acceptable cost local material temperature feedback to be made to influence local nuclear reaction speed in traveling wave neutron economy.So neutron is anti- The big negative temperature coefficient of answering property imparts the ability of the pace of control traveling wave.If seldom hot merit is extracted from burning fuel Rate, then its temperature rises and temperature-independent reactivity declines and the supercentral Fission Rate of ripple correspondingly becomes smaller and ripple Equation of time only reflect very little axial advancement rate.Similarly, if thermal power removal rate is big, material temperature declines in Sub- reactivity rises, then neutron economy becomes opposite undamped in ripple and ripple axially relatively rapidly advances.It is related can be with It is incorporated to the datail description of the illustrative implementation of the temperature feedback in the embodiment of reactor core assembly in the following literature：2006 Submission on November 28, inventor RODERICK A.HYDE, MURIEL Y.ISHIKAWA, NATHAN P.MYHRVOLD and LOWELL L.WOOD, JR., entitled " CONTROLLABLE LONG TERM OPERATION OF A NUCLEAR The U.S. Patent Application No. of REACTOR " 11/605,933, is incorporated by reference into its content hereby.

Propagation as nuclear fission traveling wave to second example of the Suggestion of the embodiment of nuclear fission traveling wave reactor, It can be with less than total fission neutron yield in whole nuclear fission traveling wave reactors.For example, without limitation as control Stick or local material-reactivity control system as thermostatic mould neutron absorber material in the block, can use nuclear fission The about 5-10% of total fission neutron yield in traveling wave reactor 10.Total fission neutron yield in nuclear fission traveling wave reactor In addition≤10% may in response in the structure member of nuclear fission traveling wave reactor high-performance, high-temperature structural material（Picture Ta, W or Re are such）Parasitic absorption and lose.It is for heat desired by the realization when being converted into electric energy this loss occur Mechanical efficiency and obtain high system security quality factor（figures-of-merit）.These materials as Ta, W or Re The Z values of material are the approximations 80% of the Z values of actinides, therefore their high-energy neutron radiative capture cross section is compared with actinides It is not especially small.The final 5-10% of total fission neutron yield in nuclear fission traveling wave reactor may be because of posting in fission product Life is absorbed and lost.However, it is contemplated that frequency spectrum may be similar to the frequency spectrum of sodium cooling fast reactor, because parasitic absorption may Only account for the about 1-2% of loss.As described above, neutron economy is characteristically abundant enough, i.e., in no leakage and rapid geometry hair In the case of dissipating, the approximation 70% of total fission neutron yield is enough traveling wave is maintained to propagate.

Propagation as nuclear fission traveling wave to the 3rd example of the Suggestion of the embodiment of nuclear fission traveling wave reactor, The high burnup of the initial actinium series fuel stock of feature as nuclear fission traveling wave（20% to about 30% is up to about, in some cases, About 40% or 50% to up to about 80% order of magnitude）, raw ore fuel can be made to obtain efficiently utilization-in addition, without reprocessing.

Note that the neutron flux of the most strong combustion zone behind burnfront make it is fissible rich on burnfront forward position Isotope area is proliferated, for nuclear fission traveling wave is made to advance.The combustion of given quality is skimmed in the burnfront of nuclear fission traveling wave After material, while carrying out fission and generating the fission product of increasing quality, as long as can be on convertible core Than the neutron radiation capture on fission-product nucleus more likely much, fissionable atom concentration continues to rise sub- radiation capture. In any particular moment, core power generation densities peak value is all in this loading area.

It will be understood that, behind nuclear fission traveling wave advance burnfront, fission-product nucleus（Its quality is averagely close to be split Become the half of core）It climbs with the concentration ratio of fissionable nucleus to can be with the ratio of fissible fission and fission product radiative capture cross section Comparable numerical value." local neutron reaction " close to negative value or in some embodiments, it may be possible to becomes negative value therewith.Therefore, fire It burns and both multiplication effectively stops.It will also be understood that it in some embodiments, can add in as boron carbide, hafnium or gadolinium Can not fission neutron absorbing material, with ensure " local neutron reaction " be negative.

In some embodiments of nuclear fission traveling wave reactor, install during reactor core assembly is manufactured and be once used in All fission fuels in reactor.In addition, in some configurations, never spentnuclear fuel is removed from reactor core assembly. In a kind of means, such embodiment may cause after nuclear fission ignition and perhaps after burnfront is propagated and completed It runs with never accessing reactor core.

In some other embodiments of nuclear fission traveling wave reactor, installed once during reactor core assembly is manufactured All fission fuels in reactor and in some configurations, never remove weary combustion from reactor core assembly Material.But will be as described below, at least some cores can be migrated or switched between the different location of reactor in-core or in the middle Fission fuel.The migration of such at least some fission fuels can be performed or switched, to realize target as discussed below.

But in some other embodiments of nuclear fission traveling wave reactor, it can will be added after nuclear fission ignition Fission fuel is added in reactor core assembly.It, can be from anti-in some other embodiments of nuclear fission traveling wave reactor It answers in heap reactor core assembly and removes spentnuclear fuel（Also, in some embodiments, removing spentnuclear fuel from reactor core assembly can be with It is carried out while nuclear fission traveling wave reactor is just in operation at power）.It is illustrative as illustrating in the following literature to add Fuel and discharge of the fuel：Submission on November 28th, 2006, inventor RODERICK A.HYDE, MURIEL Y.ISHIKAWA, NATHAN P.MYHRVOLD and LOWELL L.WOOD, JR., entitled " METHOD AND SYSTEM FOR The U.S. Patent Application No. 11/605,848 of PROVIDING FUEL IN A NUCLEAR REACTOR ", passes through reference hereby It is incorporated to its content.With whether removing that spentnuclear fuel is unrelated, the pre-expansion of original-pack fuel to skim over actinium series " combustion with nuclear fission traveling wave Any given axial member of material ", converts thereof into fission product " lime-ash ", will not make the total volume of combustion elements have any change Become actinides of the ground with the fission product substitution higher density compared with low-density.

It is provided by general introduction, nuclear fission traveling wave launcher is arrived²³²Th or²³⁸In U loading areas can utilize without limitation as Start rich in " nuclear fission ignition module " as the fission fuel assemblies of fissionable isotope.It begs in detail in the following literature The illustrative nuclear fission ignition module and method of transmitting nuclear fission traveling wave are discussed：It submits on 2 12nd, 2008, inventor CHARLES E.AHLFELD、JOHN ROGERS GILLELAND、RODERICK A.HYDE、MURIEL Y.ISHIKAWA、 DAVID G.MCALEES, NATHAN P.MYHRVOLD, CHARLES WHITMER and LOWELL L.WOOD, JR., denomination of invention For " NUCLEAR FISSION IGNITER " while co-pending U.S. patent application the 12/069th, 908, pass through reference hereby It is incorporated to its content.Higher concentration can produce more compact module, and minimum mass module can apply slowing down agent concentration ladder Degree.In addition, nuclear fission ignition module can partly pass through as preventing material for transfer for the military purposes under various situations Non-technical consideration determine.

In other means, illustrative nuclear fission igniter can contain other types of reaction source.For example, other cores are split " glowing embers " can be included by becoming igniter, for example, by being exposed in propagation nuclear fission traveling wave reactor in neutron and richness Fission fuel containing fissionable isotope.Despite the presence of the fission product " lime-ash " of various quantity, but it is such " more than burning Cinder " can play nuclear fission igniter.In other means of transmitting nuclear fission traveling wave, fissible same position can be will be enriched in The nuclear fission ignition module of element is for supplement using there may be the energetic ions of neutron again（Image quality, deuteron, α particles etc. that Sample）Or other neutron sources in the electric drive source of electronics.It, can will the grain as linear accelerator in a kind of illustrative means Sub- accelerator is positioned to that high energy proton is supplied to and may provided such neutron（For example, pass through spallation）Intermediate materials. In another illustrative means, the particle accelerator as linear accelerator can be positioned to high energy electron being supplied to and Such neutron may be provided（For example, electrofission and/or photofission by high Z elements）Intermediate materials.Alternatively It is that other known NEUTRON EMISSION process and structure as electricity induces fusion means can also provide neutron（For example, from D- The 14MeV neutrons of T fusion reactions）, can also should so as in addition to the nuclear fission ignition module for being rich in fissionable isotope Neutron propagates fission ripple for triggering.

The nucleonics of charging and nuclear fission traveling wave is now been discussed, " the core of related nuclear fission traveling wave will be then discussed Fission igniting " and the further detail below maintained.Appropriateness is rich in picture²³⁵U or²³⁹The centralized positioning of fissile material as Pu illustrates Property nuclear fission igniter, containing therefrom removing（As being issued an order electrical heating or by taking out one or more control by operating personnel Stick）Neutron absorber material（As borohydrides etc.）, and nuclear fission igniter becomes critical.Local burnup's temperature Degree rises to predetermined temperature, this after image by reactor cooling system and/or reactivity control system or local thermostat module that Sample is adjusted（It was discussed in detail in following document：Submission on November 28th, 2006, inventor RODERICK A.HYDE, MURIEL Y.ISHIKAWA, NATHAN P.MYHRVOLD and LOWELL L.WOOD, JR., entitled " AUTOMATED The U.S. Patent Application No. 12/605,943 of NUCLEAR POWER REACTOR FOR LONG-TERM OPERATION ", it is special This is incorporated by reference into its content）.It comes from²³³U or²³⁹Most of neutron of Pu fast fissions is first in part²³⁸U or²³²The upper quilts of Pu Capture.

It will be understood that, by by the radial density gradient introducing nuclear fission igniter of fire resisting moderator as image-stone ink and just Well in its fuel region, can be reduced to the enriched uranium of nuclear fission igniter will not compare light-water reactor（LWR）Fuel Much higher level.High moderator-density enables slight enriched fuel satisfactorily to burn, while reduces moderator-density and can occur Effectively fission multiplication.Therefore, the design of optimal nuclear fission igniter may involve multiplication robustness and initial criticality to from reactor core Complete ignition charge area in obtain quota power availability most short delitescence between balance.Relatively low concentration nuclear fission ignition Device brings more multiplication offsprings, therefore makes incubation period longer.

In some embodiments, the peak value reaction of reactor core assembly is slow in the first stage of nuclear fission ignition process Decline, because while total fissionable isotope storage is continuously increased, but total inventory is spatially more scattered.It is alternatively initial Fuel geometry, fuel concentration and the relation of position and fuel density are reaching it most as a result, can be arranged to maximum reaction At the time of small value still slightly just.Shortly after that, maximum reaction starts to be retained in nuclear fission igniter with substantially exceeding towards it Fissionable isotope storage breeding blanket in the corresponding maximum of fissionable isotope storage rise rapidly.For many For situation, director sphere circular casing provides maximum unit power and generates.This moment, the loading area of reactor core assembly can be claimed For " having lighted ".

It is now discussed with being referred to as the propagation of the nuclear fission traveling wave of " fission fuel burning " herein.In foregoing configuration In, before spherical diverging shell that maximum unit core power generates continues radially from nuclear fission igniter to the outer surface of loading area Into.When reaching outer surface, it generally falls into two spherical zone surfaces, and each surface is along axial two opposite directions of cylinder A respective propagation.At this moment, the maximum thermal power Production capacity of reactor core may be had evolved to.This interval is characterized For the emission period of two Propagation nuclear fission traveling wave burnfronts.In some embodiments, in igniting core loading area The heart, therefore generate two opposite propagating waves.The quality and volume of this reactor core for arranging that any given time is made all to generate power It doubles, therefore halves the generation of reactor core peak value unit power, so as to which thermotransport challenge quantitatively is reduced to minimum level.But Be, in other embodiments, as specific application is desirable, at one end on or near light a fire core loading area.It is such Means may cause single propagating wave in some configurations.

In further embodiments it is possible in multiple places igniting core loading area.It is such as special in other other embodiments Surely using desirable such, core loading area of lighting a fire on any 3D positions of heap in-core.In some embodiments, Ke Yiyin Two propagation nuclear fission traveling waves of hair, make them be propagated away from nuclear fission ignition place；But depending on geometry, nuclear fission are fired Expect composition, the action of neutron modification control structure or other considerations, can trigger and propagate different number（For example, one, three Or more）Nuclear fission traveling wave.But for the ease of understanding that the discussion of this paper refers to two without limitation with for purpose of brevity The propagation of nuclear fission traveling wave burnfront.

Reached since two ripples or during close to two opposite end points by their this forward time of outburst, nuclear energy The physics of generation is usually in the reference system of any one ripple（frame）All be inside effectively the time it is static.Ripple is advanced by fuel Speed it is directly proportional to local neutron flux, local neutron flux is linearly dependant on again to be split via the core of centering sub-control system Become the thermal power that the collective action of traveling wave neutron budget is extracted from reactor core assembly.In a kind of means, such as description exists As in following bibliography, middle sub-control system can utilize thermostat module（It is not shown）To realize：November 28 in 2006 Day submission, inventor RODERICK A.HYDE, MURIEL Y.ISHIKAWA, NATHAN P.MYHRVOLD and LOWELL L.WOOD, JR., entitled " CONTROLLABLE LONG TERM OPERATION OF A NUCLEAR REACTOR " U.S. Patent Application No. 11/605,933, be incorporated by reference into its content hereby.In other means, middle sub-control system One or more control comprising neutron absorber material and using the movement of one or more control rod drive mechanism can be utilized Stick is realized.

When needing to obtain more high-power from reactor via the lower temperature cooling agent flowed into reactor core, in some realities It applies in example, makes reactor core both ends（In some embodiments, it is closest with coolant entrance）At a temperature of drop to slightly below constant temperature mould Block designs set-point, so as to which neutron-absorbing material is filled from the corresponding son of reactor core thermostat module（sub-population）It recalls, from And increase local neutron flux, the generation of local thermal power is taken to, local material temperature is driven into setting to local thermostat module Put level a little.In some other embodiments, the variation of monitoring temperature, the shim control rod as desirable can be responded To influence temperature control.

But in double burnfront embodiments, this process is moved to two nuclear burnings in two shuntings of cooling agent It is not so significant effective to heating cooling agent before front.If the temperature of fission fuel is not excessively high（With reaching reactor core Cooling agent temperature it is unrelated）, then when being not affected by neutron-absorbing material inhibition, the reactor core dress of high level core power can be generated Play a part of temperature as defined in the design set-point of coolant heating to their module two parts in material area.Then, two Branch coolant flow, to two parts of the burning fuel of center position, therefrom removes remaining nuclear fission by two burnfronts With waste heat thermal power, both come out on the center of loading area from loading area.It is this arrange by " reduction " essentially from The multiphonon of crossing on the rear edge of each front encourages two burnfronts to be propagated to the both ends of loading area.

It is therefore contemplated that the reactor core neutronics in this configuration is substantially self-control.For example, for column heap Core embodiment, as fuel density-radius product >=200gm/cm of column reactor core²（That is, for reasonable fast neutron spectrum, For 1-2 mean free path of the neutron fission in the reactor core of typical composition）When, it is believed that reactor core nucleonics is basic On be self-control.A kind of function of neutron reflector so in Core Design can be the radiation shield substantially reduced as it Barrier, structural support member, outermost layer housing and without limitation as control rod（When being equipped with）Or thermostat module（When being equipped with When）Such reactivity control system component is such, the fast neutron fluence that the external component of reactor is seen.Neutron reflector Multiplication efficiency and unit power in outermost part that can be by improving fuel influence the performance of reactor core.Such influence The economic benefit of reactor can be improved.Without using the periphery of loading area when total energy effect is low, but they have and loading area Center comparable isotope burning it is horizontal.

It can be said that the reactor core neutronics in above-mentioned configuration is substantially self-control, but other configurations can be It is run under the control of reactor control system, which includes the appropriate electronic controller with appropriate circuitry, And it can include as one or more comprising neutron absorber material and using the movement of one or more control rod drive mechanism Appropriate Mechatronic Systems as root control rod.

Finally, carried out at any time in reactor core if it is desirable, can undesirably inject neutron inhibitor in coolant flow The irreversible negative of sub- reactivity.For example, will be as desired, it may be with as H₂Such volatility reduction agent, as BF₃That The material of sample is slightly fitted into coolant flow, can be accelerated by appearing in high temperature index therein otherwise slowly chemical anti- Answer 2BF₃+3H₂→ 2B+6HF, the substantially homogeneously deposited metal boron on the inner wall through the coolant hose of reactor core.Boron is again It is highly refractory metalloid, will not be usually migrated from its deposition station.Quantity in reactor core<100kg（Kilogram）Boron base This uniformly exists, can not involve near reactor using actuating unit negate indefinite extension interval reactor core neutron it is anti- Ying Xing.

It it is, in general, that it is appreciated by those skilled in the art that can be by varied hardware, software, solid Part and/or any combination of them body are individually and/or the various aspects described herein realized of collective can be regarded as by various types of " circuit " composition of type.Therefore, as used throughout, " circuit " includes but not limited to the electricity containing at least one discrete circuit Road, the circuit containing at least one integrated circuit, the circuit containing at least one application-specific integrated circuit, formation are by computer program The universal computing device of configuration（For example, by least partly realizing that the computer program of process and/or equipment as described herein is formed All-purpose computer or the microprocessor that is formed by least partly realizing the computer program of process and/or equipment as described herein Device）Circuit, formed storage device（For example, various forms（For example, arbitrary access, flash, read-only etc.）Memory）Electricity Road, and/or formation communication equipment（For example, modem, communication switchboard, opto-electronic conversion equipment etc.）Circuit.This field Those of ordinary skill it should be appreciated that theme as described herein can be in a manner of analog or digital or combination thereof is real It is existing.

It is, in general, that it is appreciated by those skilled in the art that various embodiments described herein can pass through Various types of Mechatronic Systems individually and/or collective realize, the Mechatronic Systems contain as hardware, software, firmware, and/or they Substantially any assembly as varied electrical components；And as rigid body, elasticity or torsion body, hydraulic system, electromagnetism cause Dynamic equipment, and/or their substantially any assembly are such, can transfer varied component of mechanical force or movement.Therefore, As used throughout, " Mechatronic Systems " include but not limited to operationally with energy converter（For example, actuator, motor, piezo crystals Body, MEMS（MEMS）Deng）The circuit of coupling, the circuit containing at least one discrete circuit are integrated containing at least one The circuit of circuit, the circuit containing at least one application-specific integrated circuit form the universal computing device being made of computer program （The all-purpose computer that is made of the computer program at least partly realizing process and/or equipment as described herein or by least portion The microprocessor that the computer program for realizing process and/or equipment as described herein is divided to form）Circuit, formed storage device （For example, various forms（For example, arbitrary access, flash, read-only etc.）Memory）Circuit, formed communication equipment（For example, it adjusts Modulator-demodulator, communication switchboard, opto-electronic conversion equipment etc.）Circuit, and/or any non-electrical as light or other analogs Analog.Those of ordinary skill in the art will also be understood that the example of electric system includes but not limited to miscellaneous consumption Electron-like system, Medical Devices and as motorized transport systems, factory automation system, security system, and/or communication/calculating Other systems as system.It is appreciated by those skilled in the art that as used herein Mechatronic Systems may not The system with electric actuation and mechanically actuated the two is confined to, unless otherwise indicated by context.

Exemplary embodiments

Since having been presented for the general introduction of initiation and propagation in relation to nuclear fission traveling wave, said now by non-limitative example Bright exemplary embodiments.

It is hereafter to describe a series of these flow charts realized.In order to make it easy to understand, these flow charts are organized into initially Flow chart shows the realization via exemplary realization, and hereafter, flow chart displaying then is more early in one or more as establishing Show alternate embodiments and/or the expansion of the initial flowchart of on flow chart, sub-unit operation or additional component operation. Those of ordinary skill in the art will be understood that, displaying style used herein（For example, from the flow chart for showing exemplary realization Displaying starts, and additional detail and/or further detail below are hereafter provided in subsequent flow）It is usually rapid for the ease of people With will be readily understood that various processes realize.In addition, those of ordinary skill in the art should will further appreciate that, exhibition used herein Show that style is also adapted with modularization and/or Object-oriented Programming Design normal form.

For referring now to Figure 1A and by general introduction, exemplary methods 10 are carried for operation nuclear fission traveling wave reactor It supplies.Further referring to Figure 1B, citing ground rather than the illustrative nuclear fission for restrictively showing nuclear fission traveling wave reactor The component of traveling wave reactor core 12.Fission fuel subassembly 14 is accommodated in reactor core assembly 16.In order to help For the sake of clear, Figure 1B may instantiate all fission fuels that can be accommodated in the embodiment of reactor core assembly 16 The part of subassembly 14.

Reference system is defined in reactor core assembly 16（reference of frame）.In some embodiments, join According to being that can be defined by x dimension, y-dimension and z-dimension.In some other embodiments, reference system can be tieed up by radial direction Degree is defined with axial dimension.In some other embodiments, reference system can include axial dimension and transverse dimensions.

In some embodiments, fission fuel subassembly 14 can be single as fission fuel stick, plate, ball etc. Only fission fuel element.In some other embodiments, fission fuel subassembly 14 can be fission fuel assemblies- That is, two or more independent fission fuel elements for being grouped into a component.With fission fuel subassembly 14 Embodiment it is unrelated, the fission fuel in fission fuel subassembly 14 can be as described above any suitable The fission fuel of type.

For general introduction, method 10 is since frame 18.In frame 20, in nuclear fission traveling wave reactor core 12 In fission fuel subassembly 14 in reactor core assembly 16, make nuclear fission traveling wave burnfront 22 along first and second Dimension is propagated（As arrow 24 is signified）.In frame 26, to limit nuclear fission along the second dimension according to the constraint of selected group of dimension The mode of the shape of traveling wave burnfront 22 is migrated along the first dimension from respective first position is to the respective second position controllable Fission fuel subassembly 14 it is selected several.Terminate this method 10 in frame 28.

Exemplary details are illustrated by non-limitative example now.

It fission fuel subassembly 14 and is designated as the dimensions of the first and second dimensions there are spatial relationships.For example, one In a little embodiments, fission fuel subassembly 14 can be extended along the second dimension.In some embodiments, the second dimension can be with It is y-dimension or axial dimension.In some other embodiments, the second dimension can be x dimension, y-dimension or transverse dimensions.

In addition, in some embodiments, the first dimension can be almost orthogonal with the axis of elongation of fission fuel subassembly 14. In some embodiments, the first dimension and the second dimension can be almost mutually orthogonal.

Various dimensions can be designated as the first dimension and the second dimension.For example, in some embodiments, the first dimension can To include radial dimension, and the second dimension can include axial dimension.In some other embodiments, the first dimension can include Axial dimension, and the second dimension can include radial dimension.In some embodiments, the first dimension can include axial dimension, And the second dimension can include transverse dimensions.In some other embodiments, the first dimension can include transverse dimensions, and second Dimension can include axial dimension.In the column heap that as the configuration of typical commercial light-water reactor, component axially extends In core, the first dimension can be radial dimension, and the second dimension can be axial dimension.In matching somebody with somebody as CANDU heavy water reactors It puts in such other reactor configurations, fuel assembly can be extended along the first dimension, and can be along laterally or radially Second dimension moves.

As illustrated in Figure 1B, can according to each attribute by the position characterization in reactor core 12 into first position and the Two positions.It is, in general, that a position is considered one of the reactor core 12 around fission fuel subassembly 14 One space of a areas adjacent.One position generally can also be considered as just in the reactor core 12 it is any to Determine a space in region or be considered most of region of reactor core 12.For example, and referring additionally to figure 1C, in some embodiments, first position, which can include outer position 30 and the second position, can include inner position 32.Such as Illustrated in Fig. 1 C, in some embodiments, inner position 32 and outer position 30 can be based on the centers with reactor core 12 Partial geometry proximity.In some other embodiments, inner position and outer position can be based on neutron flux so that inner Neutron flux on the position of face is more than the neutron flux on outer position.In some other embodiments, inner position and outside Position can be based on reactivity so that the k on inner position_effectiveMore than the k on outer position_effective.It is anti-to represent traveling wave Answer the embodiment of heap that there can be the outer position of the outside for being included in propagating wave or the position along the direction of propagating wave, and Inner position can include nuclear fission traveling wave by or by position.

It is provided by further example and referring additionally to Fig. 1 D, in some embodiments, first position can include Inner position 32 and the second position can include outer position 30.As illustrated in Fig. 1 D, in some embodiments, inner position 32 It can the geometry proximity based on the central part with reactor core 12 with outer position 30.In some other embodiments, Inner position and outer position can be based on neutron flux so that during the neutron flux on inner position is more than on outer position Sub- flux.In some other embodiments, inner position and outer position can be based on reactivity so that on inner position k_effectiveMore than the k on inner position_effective.In other embodiments, can with occur in those regions account for it is leading Nuclear reaction come describe inwardly and outer position.It is provided by nonrestrictive example, inner position can be split by accounting for leading core Become reaction to characterize, and outer position can pass through accounting for leading core absorbing reaction and characterize on fertile material.

, first position and the second position unrelated into inner position or outer position are characterized with by first position and the second position It can be characterized according to other attributes.For example, in some embodiments, first position and the second position can be along the first dimensions It is on the opposite side of reference value.In some other embodiments, first position and the second position can include substantially equilibrium At least one attribute.For example, substantially balanced at least one attribute can include the geometry with the central part of reactor core Proximity, neutron flux, reactivity etc..

It is provided by nonrestrictive example and with reference to Fig. 1 E, can be axially confined with being constrained according to selected group of dimension The mode of the shape of nuclear fission traveling wave burnfront 22 radially outwardly may be used from respective inner position 32 to respective outer position 30 Control migration fission fuel subassembly（For clarity, it is not shown）It is selected several.It is provided without limitation by illustrating, Show the shape of nuclear fission traveling wave burnfront 22 with fission fuel subassembly（It is not shown）Radial motion axial change Change.Left figure instantiates the original shape of nuclear fission traveling wave burnfront 22, will be understood that, for clarity, merely illustrates core and splits Become a quarter perimeter of traveling wave burnfront 22.

In middle figure, in selected fission fuel subassembly（It is not shown）It has burnt after the desired time or according to wishing Hope reactivity parameter（Without limitation as burnup）, by selected fission fuel subassembly（It is not shown）Position from the inside 32 radial migrations are put to outer position 30.Reactivity is from the peak position being radially on inner position 32（As shown in the left diagram）Footpath To being moved outwardly to outer position 30（As shown in middle figure）.

Within the service life of nuclear fission traveling wave reactor core 12, outer position 30 can be arrived radially outward in position 32 from the inside Migrate other fission fuel subassembly（It is not shown）.As so in addition to external migration as a result, nuclear fission can be prevented Fission fuel subassembly in traveling wave reactor core 12 on radially internal position（It is not shown）, burning must be than nuclear fission traveling wave Fission fuel subassembly in reactor core 12 in radially external position（It is not shown）It is more.As shown at right, if as above Described radially outward to have migrated sufficient amount of fission fuel subassembly, then the shape of nuclear fission traveling wave burnfront 22 can be with It is similar to Bezier（Bessel）Function.In addition, if sufficient amount of fission fuel is radially outward migrated as described above Subassembly, then all or almost all fission fuel subassemblies in nuclear fission traveling wave reactor core 12 can almost simultaneously Ground reaches or close to their own burnup limit.It in this case, can be in nuclear fission traveling wave reactor core 12 Farthest use fission fuel subassembly.

It is provided by another non-limitative example and with reference to Fig. 1 F, it can be axial to be constrained according to selected group of dimension The mode of the shape of nuclear fission traveling wave burnfront 22 is limited, from respective inner position 32 to respective outer position 30 radially outward Ground controllably migrates selected several the 14 of fission fuel subassembly, and from respective outer position 30 to respective 32 footpath of inner position To other selected several the 14 ' of upcountry controllable migration fission fuel subassembly.That is, inside position 32 and outside Fission fuel subassembly 14 and 14 ' selected by being exchanged between position 30.

It is provided without limitation by illustrating, shows the shape of nuclear fission traveling wave burnfront 22 with fission fuel point Such Axial changes for exchanging radial motion of component 14 and 14 '.Left figure instantiates the initial of nuclear fission traveling wave burnfront 22 Shape.In left figure, fission fuel subassembly 14 contains the fissible inclusion than fission fuel subassembly more than 14 '.Example Such as, fission fuel subassembly 14 may be the part of the ignition module of nuclear fission traveling wave reactor core 12.Lift another example For son, fission fuel subassembly 14 may include being used as absorbs fast spectrum neutron in nuclear fission traveling wave reactor core 12 Subsequent transmuting is into fertile isotope as a result, the regenerated fissile material from fertile isotope material.On the contrary, core Fission fuel subassembly 14 ' contains the fissible inclusion fewer than fission fuel subassembly 14.In some cases, nuclear fission Fuel subassembly 14 ' can include the fertile isotope inclusion than fission fuel subassembly more than 14.In such situation Under, fission fuel subassembly 14 ' can more absorb fast spectrum neutron than fission fuel subassembly 14.

In right figure, by selected fission fuel subassembly 14, position 32 radially outward moves to outside position from the inside 30 are put, and position 30 radially-inwardly moves to inner position 32 from the outside by selected fission fuel subassembly 14 '.In interaction Fission fuel subassembly 14 and 14 ' afterwards, make the axial distribution of nuclear fission traveling wave burnfront 22 with before so exchanging The axial distribution of nuclear fission traveling wave burnfront 22（Referring to left figure）Compared to it is more compact evenly.As a result, in some implementations Can be that nuclear fission traveling wave burnfront 22 is realized generally uniform distribution or is uniformly distributed in example.In some other embodiments, It may not want that and realize generally uniform distribution for nuclear fission traveling wave burnfront 22 or be uniformly distributed.In this case, may be used It can only want to reposition fissile material or reposition fertile isotope material.In some other embodiments, may Wish along radial dimension extension nuclear fission traveling wave burnfront 22.

Referring additionally to Fig. 1 G, can also fission fuel along radial dimension be migrated by such as reference chart 1F discussion above Subassembly 14 and 14 ' limits the shape of nuclear fission traveling wave burnfront 22 in radial dimension.Nuclear fission traveling wave burnfront 22 Radial distribution, which may be considered that, represents neutron leakage neutron current.The left figure and right figure of Fig. 1 G show the left side for corresponding respectively to Fig. 1 F The view of the axially dimension of figure and right figure.

It, can be with according to the radially defined nuclear fission traveling wave burnfront 22 of selected group of dimension constraint referring now to Fig. 1 H The mode of shape is laterally controllably migrated selected by fission fuel subassembly 14 from respective first position to the respective second position It is several.

Left figure instantiates the original shape of the axially nuclear fission traveling wave burnfront 22 of dimension viewing, selected nuclear fission Fuel subassembly 14 is in the first position z, r, φ₁On.In the example shown in the purpose for illustration, fission fuel grouping Part 14 is in first position z, r, φ₁On contribute to for some reason, may be confirmed as be more than in first position z, r, φ₁On The reaction of desirable reacting dose.For example, fission fuel subassembly 14 may be the point of nuclear fission traveling wave reactor core 12 The part of fiery component.For another example, fission fuel subassembly 14 may include reacting as in nuclear fission traveling wave The fast spectrum subsequent transmuting of neutron is absorbed in heap reactor core 12 into fertile isotope as a result, from fertile isotope material Regenerated fissile material.As a result, nuclear fission traveling wave burnfront 22 may be too much along first position z, r, φ₁'s Radial propagation.

As shown at right, selected fission fuel subassembly 14 is along transverse dimensions φ from first position z, r, φ₁ Lateral transfer is to second position z, r, φ₂.It will be understood that, as selected fission fuel subassembly 14 from first position z, r, φ₁It is horizontal To moving to second position z, r, φ₂As a result, the radially defined shape of nuclear fission traveling wave burnfront 22.Selected core Fission fuel subassembly 14 is from first position z, r, φ₁Lateral transfer is to second position z, r, φ₂From first position z, r, φ₁It moves Second position z, r, φ are added in except fissible inclusion, and by fissible inclusion₂In.As shown at right, nuclear fission traveling wave The shape of burnfront 22 is in first position z, r, φ₁Nearby shortened along radial dimension r, and in second position z, r, φ₂It is attached It is closely elongated along radial dimension r.

It is controllable to migrate fission fuel point along the first dimension from respective first position to the respective second position in frame 26 Selected several possible one or more processes of needs of component 14.For example, and referring additionally to Fig. 1 I and 1J, in some embodiments In, in frame 26 fission fuel subassembly to the respective second position is controllably migrated along the first dimension from respective first position 14 it is selected several, can include as arrow 36 is signified（Fig. 1 J）, rotated in frame 34 selected by fission fuel subassembly 14 Several is at least one.Will be understood that, as desired, rotated in frame 34 selected by fission fuel subassembly 14 it is several at least It one, can be carried out using any appropriate reactor core fuel management system.Further it may be desired to rotate selected fission fuel point Component 14, farthest to reduce or prevent the change of the reactor structural material as the bending of fission fuel subassembly Shape.

For for another example and referring additionally to Fig. 1 K and 1L, in some other embodiments, in frame 26 along First dimension from respective first position is to the respective second position controllably several selected by migration fission fuel subassembly 14 can To include as arrow 40 is signified（Fig. 1 L）, overturned in frame 38 several at least one selected by fission fuel subassembly 14. It will be understood that, as desired, at least one can utilize several selected by fission fuel subassembly 14 is overturned in frame 38 and is appointed What appropriate reactor core fuel management system carries out.Reverse fission fuel subassembly 14 can cause fission fuel subassembly 14 Entrance（Before reverse）Become the outlet of fission fuel subassembly 14（After reverse）, vice versa.Such overturn can To cause on the end of fission fuel subassembly 14 to the axially uniform thermal stress and/or spoke of fission fuel subassembly 14 Projection is rung.Any such radiation effect all may be that temperature is relevant and/or shaft end with fission-type reactor reactor core 12 on Neutron flux variation it is related.It will be understood that, the reverse of fission fuel subassembly 14 causes reverse fission fuel to be grouped The both ends of part 14 surround reverse central point and move to the second position from first position.But in some cases it is also possible to wish The laterally position of change component.

It will also be understood that for specific application any one or more dimensions can be selected to constrain as desired.For example, at some In embodiment, selected group of dimension constraint can include the predetermined maximal distance along the second dimension.

In some other embodiments, selected group of dimension constraint can be the function of at least one burnfront criterion. For example, burnfront criterion can include neutron flux.In some arrangements, neutron flux and fission fuel can be grouped Part 14 it is selected several at least one associated.In some other embodiments, burnfront criterion can include neutron note Amount（fluence）.It, can be by selected by neutron fluence and fission fuel subassembly 14 several at least one in some arrangements It is a associated.

In some other embodiments, burnfront criterion can include burnup.Some arrangement in, can by burnup with Fission fuel subassembly 14 it is selected several at least one associated.In such arrangement, it may be desirable to by nuclear fission The selected of fuel subassembly 14 several is moved to the second with the second burn-up rate from the first position with the first burn-up rate It puts.If selected fission fuel subassembly 14 will terminate its service life, first position can be by high burnup rate The position of characterization, and the second position can be by reduction burn-up rate（Compared with the high burnup rate on first position）Or almost zero Burn-up rate characterization position.In the embodiment being proliferated in fission fuel subassembly 14, it may be desirable to fire nuclear fission Material subassembly 14 is moved to from the first position with low burn-up rate with high burnup rate（Compared with the burn-up rate of first position） The second position.

In some other embodiments, burnfront criterion can include the selected several of fission fuel subassembly 14 Burnfront position at least one.Burnfront position can be fired by nuclear fission traveling wave reactor core 12 or nuclear fission The feature in subassembly 14 is expected to characterize.Such feature can include but is not limited to fission rate, proliferation rate, power output, temperature Degree, reactivity etc..

It will be understood that, along the first dimension from respective first position, to the respective second position controllably migration core is split in frame 26 Become fuel subassembly 14 it is selected several, can by specific application it is desirable it is any in a manner of carry out.For example, and other parameter Fig. 1 M（It is signified with such as Fig. 1 C and 1D）, in some embodiments, along the first dimension from respective first position to each in frame 26 It is from the second position controllably several selected by migration fission fuel subassembly 14, it can be included in frame 42 along the first dimension It is radially controllably migrated from respective first position to the respective second position several selected by fission fuel subassembly 14.It will understand , as desired, the radial migration in frame 42 can be carried out using any appropriate reactor core fuel management system.

In some other embodiments and referring additionally to Fig. 1 N and 1O, along the first dimension from respective in frame 26 One position is to the respective second position controllably several selected by migration fission fuel subassembly 14 to be included such as 46 institute of arrow Refer to, fission fuel point is spirally controllably migrated from respective first position to the respective second position along the first dimension in frame 44 Component 14 it is selected several.It will be understood that, as desired, the spiral migration in frame 44 can utilize any appropriate reactor core internal combustion expects pipe Reason system carries out.

In some other embodiments and referring additionally to Fig. 1 P and 1Q, along the first dimension from respective in frame 26 One position is to the respective second position controllably several selected by migration fission fuel subassembly 14 to be included such as 50 institute of arrow Refer to, fission fuel point is axially controllably migrated from respective first position to the respective second position along the first dimension in frame 48 Component 14 it is selected several.It will be understood that, as desired, the axial migration in frame 48 can utilize any appropriate reactor core internal combustion expects pipe Reason system carries out.

It will be understood that, the shape of nuclear fission traveling wave burnfront 22 can be by without limitation as neutron flux, neutron are noted Amount, burnup, and/or reactivity（Or their any ingredient）Like that, it is associated any with nuclear fission traveling wave burnfront 22 Parameter limits.It will also be understood that nuclear fission traveling wave burnfront 22 can have such as the desirable any shape of specific application.Example Such as and referring additionally to Fig. 1 R, in some embodiments, the shape of nuclear fission traveling wave burnfront 22 can be approximately spherical 's.In some other embodiments and referring additionally to Fig. 1 S, the shape of nuclear fission traveling wave burnfront 22 can connect with selected Continuous curved surface is substantially consistent.In some embodiments and referring additionally to Fig. 1 T, the shape of nuclear fission traveling wave burnfront 22 Can surround the first dimension substantially rotational symmetry.In some other embodiments and referring additionally to Fig. 1 U and 1V, core is split The shape for becoming traveling wave burnfront 22 can have the substantially n fold rotational symmetry for surrounding the second dimension.

Those of ordinary skill in the art know, substantially constant, " flat " combustion distribution is kept across reactor core（Picture Bessel function is such）The power peak between the fission fuel subassembly of heap in-core is farthest reduced, and is improved The utilization rate of fuel.In traveling wave fission-type reactor, as described above, the size of the combustion zone of reactor becomes due to high-conversion rate To in expansion.Combustion zone keeps the sufficient feed-in nuclear material as fertile isotope material or fissile material, to protect Hold high-conversion rate.

It will be understood that in the configuration of some reactors, exist and migrate fission fuel subassembly as described above to keep The advantages of wishing reactor burnfront feature.For example, fission fuel subassembly radial migration can be risen into combustion zone The effect for the reaction zone that fertile isotope material or fissile material are supplied.It is moved radially outward fission fuel subassembly It can be used for being moved to the fission fuel subassembly for having arrived at its burnup limit beyond the region of high neutron activity.Radially It is displaced outwardly can be used for reducing burning by the way that fissible, incendivity fissionable fuel is made to be diffused into non-burning region in the past The power density in region.It will be understood that, will move radially to combine with spiral movement allows to shape more for the further of burnfront Careful spiral increases to be moved radially with what orientation movement combined.It will also be understood that, in some cases it may by fission fuel Subassembly is exchanged with the fission fuel subassembly in other positions（Or it exchanges）.In this case, can will come from can The fertile isotope material in conversion blanket area is exchanged with carrying out the material of grilling thoroughly of autothermal reactor combustion zone, in other cases, can be with The fission fuel from direct neighbor reactor core position is exchanged, so that two or more fission fuel subassemblies are handed over Change place.

In some embodiments and referring additionally to Fig. 1 W, shape of the nuclear fission traveling wave burnfront 22 along the second dimension Can be asymmetrical.In some arrangements, the shape of nuclear fission traveling wave burnfront 22 can surround the rotation of the second dimension not Symmetrically.

In some embodiments and referring additionally to Fig. 1 X, method 20, which is additionally may included in frame 52, utilizes nuclear fission traveling wave Ignition module（It is not shown）Trigger nuclear fission traveling wave burnfront 22.Trigger nuclear fission traveling wave using nuclear fission traveling wave ignition module The il-lustrative example of burnfront has already discussed above, here without repeating.Referring additionally to Fig. 1 Y, in frame 54 can along First dimension from respective first position to the respective second position controllably migrate fission fuel subassembly selected by several Forward It is at least one except nuclear fission traveling wave ignition module.Referring additionally to Fig. 1 Z, in some embodiments, along first in frame 54 Dimension from respective first position to the respective second position controllably migrate fission fuel subassembly selected by it is several before, remove core Fission at least one of traveling wave ignition module can include：In frame 56 along the first dimension from respective first position to respective The second position controllably migrate fission fuel subassembly it is selected it is several before, the igniting of nuclear fission traveling wave is removed from the second position Component it is at least one.

In some embodiments and referring additionally to Figure 1A A, in block 58, along the first dimension from respective first position To the respective second position controllably migrate selected by fission fuel subassembly it is several before, nuclear fission traveling wave reactor is made to become sub- It is critical.For example, and referring additionally to Figure 1A B, in some embodiments, nuclear fission traveling wave reactor is made to become Asia in block 58 and is faced Boundary can include in block 60 will be in neutron absorber material intercalation reaction heap reactor core.

It, in some embodiments, can be along the first dimension from respective first position in frame 62 referring additionally to Figure 1A C To the respective second position controllably migrate selected by fission fuel subassembly it is several after, re-establish critical.It is for example, and another External reference Figure 1A D in some embodiments, re-establish critical can include in block 64 from reactor core in frame 62 Remove at least part of neutron absorber material.

It in some embodiments and referring additionally to Figure 1A E, can be along the first dimension from respective first in frame 66 Position to the respective second position controllably migrate selected by fission fuel subassembly it is several before, close the reaction of nuclear fission traveling wave Heap.It, can be controllable from respective first position to the respective second position along the first dimension in frame 68 referring additionally to Figure 1A F Migrate fission fuel subassembly it is selected it is several after, restart nuclear fission traveling wave reactor.

Referring now to Fig. 2A and 1B, exemplary methods 200 be in order to control nuclear fission traveling wave burnfront 22 along the first He Second dimension propagate nuclear fission traveling wave reactor and provide.Method 200 is since frame 202.In frame 204, in nuclear fission In fuel subassembly 14, constrained according to selected group of dimension along the second dimension and determine wishing for nuclear fission traveling wave burnfront 22 Hope shape.In block 206, in a manner of shape desired by response, determine fission fuel subassembly 14 it is selected it is several along Migration of first dimension from respective first position to the respective second position.

Referring additionally to Fig. 2 B, in some embodiments, in block 210, the existing of nuclear fission traveling wave burnfront 22 is determined Shape.Will be understood that, as desired, determine the existing shape of nuclear fission traveling wave burnfront 22 in block 210, can in frame Determine that the desired shape of nuclear fission traveling wave burnfront 22 relatively carries out in 204.In some embodiments, in block 210 It determines the existing shape of nuclear fission traveling wave burnfront 22, nuclear fission traveling wave burnfront 22 can be being determined in frame 204 It is carried out before desired shape.In some other embodiments, the existing of nuclear fission traveling wave burnfront 22 is determined in block 210 Shape can be almost carried out at the same time with determining the desired shape of nuclear fission traveling wave burnfront 22 in frame 204.At some its In its embodiment, the existing shape of nuclear fission traveling wave burnfront 22 is determined in block 210, core can be being determined in frame 204 It is carried out after the desired shape of traveling wave of fissioning burnfront 22.As desired, can include determining that fission rate, estimation burnup, Proliferation rate, Temperature Distribution, power distribution, assembly operating history and respective reactivity of the fission fuel of having moved in position Determine desired shape to value.

It will be understood that, can be desired shape and/or holding nuclear fission row as establishing nuclear fission traveling wave burnfront 22 The desired shape of ripple burnfront 22 is such, the desirable any purpose migration fission fuel subassembly 14 of specific application It is selected several.For example, in some embodiments and referring additionally to Fig. 2 C, in block 206 in a manner of shape desired by response, Determine selected several moving from respective first position to the respective second position along the first dimension of fission fuel subassembly 14 It moves, it can be including in a manner of shape desired by foundation, determining selected several edges of fission fuel subassembly 14 in block 212 Migration of first dimension from respective first position to the respective second position.In some other embodiments and referring additionally to figure 2D in block 206 in a manner of shape desired by response, determines the selected several along the first dimension of fission fuel subassembly 14 The migration from respective first position to the respective second position is spent, can be included in block 214 in a manner of shape desired by holding, Determine selected several moving from respective first position to the respective second position along the first dimension of fission fuel subassembly 14 It moves.

It will be understood that, inter alia, it is also possible to be desired to determine carrying out the time of desired migration.For this purpose, and reference Fig. 2 E in some embodiments, in block 216 in a manner of shape desired by response, are determined along the first dimension from respective the Several time selected by one position to respective second position migration fission fuel subassembly 14.It will also be understood that as desired, It can make in frame 216 and determine on any point of execution method 200.

In some embodiments, the selected several of fission fuel subassembly 14 can be migrated.Referring additionally to Fig. 2 F, in frame It can be migrated in 218 in a manner of shape desired by response along the first dimension from respective first position to the respective second position Fission fuel subassembly 14 it is selected several.

It will be understood that, some aspects of frame 200 are similar to some aspects of the method 10 illustrated above.These similar aspects It will be mentioned, but for simplicity, without illustrating their details to understand.

For example, and referring additionally to Figure 1B, in some embodiments, fission fuel subassembly 14 can be along the second dimension Degree elongation.First dimension can be almost orthogonal with the axis of elongation of fission fuel subassembly 14.First dimension and the second dimension can With almost mutually orthogonal.

In further example and in addition referring still to Figure 1B, the first dimension can include radial dimension, and second Dimension can include axial dimension.In some other embodiments, the first dimension can include axial dimension, and the second dimension can To include radial dimension.Any kind of fission-type reactor can include the fission fuel point for extending through entire axial dimension Component and multiple fission fuel subassemblies extend through radial dimension.Nuclear fission traveling wave can be to depend on, in such case Under, depending on power distribution and diverging of the nuclear fission traveling wave from interior zone to perimeter, different from along radial dimension Rate axially propagate by dimension, especially in the configuration of column reactor core.Progress core is may want in this case to split Become the radial migration of fuel subassembly, to protect the waveform and feature of axially dimension.For example, propagate nuclear fission traveling wave Axial range to reactor region will promote neutron to be leaked out on the shaft end of reactor core from reactor core.As above Described, such leakage, which is reduced in fission-type reactor, can be switched to fissible conversion.It is swollen burnfront can be moved radially The swollen fission fuel subassembly to unwished-for axial position, so that fission fuel subassembly is by fission fuel subassembly The neutron activity that interior, reduction or limitation burnfront are propagated further on the place in unwished-for place dominates.In other feelings Under condition, it may be desirable to fission fuel subassembly is moved radially according to the propagation of the nuclear fission traveling wave of axially dimension, in order to The fissile material in the axial region for having regenerated fission fuel subassembly is used in fission-type reactor reactor core In other parts.On given axial position, can burnfront be made along footpath by controlled displacement fission fuel subassembly It is heterogeneous to dimension, so as to as desired, concentration alternately variation zone can be established.Highly enriched area is close to dilution or low concentration The neutron that highly enriched area is made to leak into low enrichment region is placed in area to be increased, so as to which help fertile isotope material being converted into can Fissioner.Will be understood that, above-mentioned migration can promote along the propagation of the first dimension and with limiting the propagation along the second dimension It carries out.

In some further examples and in addition referring still to Figure 1B, the first dimension can include axial dimension, and the Two-dimensions can include transverse dimensions.In other examples, the first dimension can include transverse dimensions, and the second dimension can wrap Include axial dimension.

As discussed above and referring additionally to Fig. 1 C, first position can include outer position 30 and the second position can To include inner position 32.In addition as discussed above, inner position 32 and outer position 30 can be based on and reactor core The geometry proximity of 12 central part.Inner position 32 and outer position 30 can be based on neutron flux so that inner position Neutron flux on 32 is more than the neutron flux on outer position 30.As discussed above, inner position 32 and outer position 30 It can be based on reactivity so that the k on inner position 32_effectiveMore than the k on outer position 30_effective。

In some embodiments and referring additionally to Fig. 1 D, first position can include inner position 32 and the second position It can include outer position 30.Inner position and outer position can be connect based on the geometry of the central part with reactor core 12 Nearly property and/or based on neutron flux so that the neutron flux on inner position be more than neutron flux on outer position and/or Based on reactivity so that the k on inner position_effectiveMore than the k on outer position_effective。

In some embodiments and as shown in Figure 1B, first position and the second position can be in ginseng along the first dimension It examines on the opposite side of value.

In addition as shown in Figure 1B, in some embodiments, first position and the second position can include substantially equilibrium extremely A few attribute.For example, at least one attribute can include geometry proximity, the neutron with the central part of reactor core 12 Flux, and/or reactivity.

In some embodiments and referring additionally to Fig. 2 G, in block 206, the selected of fission fuel subassembly 14 is determined Several migrations along the first dimension from respective first position to the respective second position can be included in frame 220, determine that core is split Become selected several at least one rotation of fuel subassembly 14.In some embodiments and referring additionally to Fig. 2 H, in frame In 206, the selected several along the first dimension from respective first position to respective second of fission fuel subassembly 14 are determined The migration put can be included in frame 222, determine the selected several at least one reverse of fission fuel subassembly 14.

In some embodiments, selected group of dimension constraint can include the predetermined maximal distance along the second dimension. In some other embodiments, selected group of dimension constraint can be the function of at least one burnfront criterion.For example, burning battle array Face criterion can include it is nonrestrictive, as selected by with fission fuel subassembly 14 it is several it is at least one it is associated in Neutron flux as sub- flux.As another example, burnfront criterion can include it is nonrestrictive, as with nuclear fission Neutron fluence as selected several at least one associated neutron fluence of fuel subassembly 14.As another example Son, burnfront criterion can include nonrestrictive, several at least one as selected by with fission fuel subassembly 14 Burnup as associated burnup.In some other embodiments, burnfront criterion can include fission fuel grouping Selected several at least one interior burnfront position of part 14.

Referring additionally to Fig. 2 I, in some embodiments, in block 206, the selected several of fission fuel subassembly 14 are determined A migration along the first dimension from respective first position to the respective second position can be included in frame 224, determine nuclear fission Selected several radial migrations along the first dimension from respective first position to the respective second position of fuel subassembly 14.One In a little embodiments and referring additionally to Fig. 2 J, in block 206, the selected several along first of fission fuel subassembly 14 are determined Migration of the dimension from respective first position to the respective second position, can be included in frame 226, determine fission fuel subassembly 14 selected several spiral migrations along the first dimension from respective first position to the respective second position.In some other implementations In example and referring additionally to Fig. 2 K, in block 206, determine fission fuel subassembly 14 it is selected it is several along the first dimension from Respective migration of the first position to the respective second position, can be included in frame 228, determine the institute of fission fuel subassembly 14 Select several axial translations.

Referring additionally to Fig. 2 L, in some embodiments, determined in frame 204 desired by nuclear fission traveling wave burnfront 22 Shape can be included in frame 230 and determine the approximately spherical of nuclear fission traveling wave burnfront 22.In some other embodiments with And referring additionally to Fig. 2 M, the desired shape of nuclear fission traveling wave burnfront 22 is determined along the second dimension in frame 204, it can be with It is included in the continuous bend surface shape that nuclear fission traveling wave burnfront 22 is determined in frame 232.In some other embodiments, may be used So that curved surface expands the surface area of burnfront.In such embodiments, combustion zone is made to leak into the neutron of breeding blanket Increase.

The desired shape of nuclear fission traveling wave burnfront 22 can be any shape.As discussed above, in various realities It applies in example, the desired shape of nuclear fission traveling wave burnfront 22 can surround the second dimension substantially rotational symmetry；Core is split The desired shape for becoming traveling wave burnfront 22 can have the substantially n fold rotational symmetry for surrounding the second dimension；Nuclear fission row The desired shape of ripple burnfront 22 can be asymmetrical；And/or the desired shape of nuclear fission traveling wave burnfront 22 Can be rotationally asymmetric around the second dimension.In some other embodiments, the symmetric shape of n weight symmetries can be converted Into the discrete combustion zone of nuclear fission traveling wave reactor in-core.For example, can be transformed into burnfront can be propagated further To n or less discrete（That is, neutron decouples）Combustion zone（Referring to Fig. 1 V）Lobe.

Some embodiments can be provided as illustrative system.For example, and referring now to Fig. 3 A, illustrative system 300 be to determine fission fuel subassembly（It is not shown in Fig. 3 A）Migration and provide.Pass through nonrestrictive example It provides, system 300 can provide execution method 200（Fig. 2A -2M）Appropriate system environments.In some embodiments and in addition With reference to Figure 1B, for the nuclear fission traveling wave burnfront 22 propagated along the first and second dimensions, circuit 302 is configured in core Dimension in fission fuel subassembly 14 according to selected group constrains, nuclear fission traveling wave burnfront 22 is determined along the second dimension Desired shape.Circuit 304 is configured in a manner of shape desired by response, determines the selected of fission fuel subassembly 14 Several migrations along the first dimension from respective first position to the respective second position.

It it is, in general, that it is appreciated by those skilled in the art that can be by varied hardware, software, solid Part and/or any combination of them body are individually and/or the various aspects described herein realized of collective can be regarded as by various types of " circuit " composition of type.Therefore, as used throughout, " circuit " includes but not limited to the electricity containing at least one discrete circuit Road, the circuit containing at least one integrated circuit, the circuit containing at least one application-specific integrated circuit, formation are by computer program The universal computing device of composition（It is made of the computer program at least partly realizing process and/or equipment as described herein logical The microprocessor formed with computer or by least partly realizing the computer program of process and/or equipment as described herein）'s Circuit forms storage device（For example, various forms（For example, arbitrary access, flash, read-only etc.）Memory）Circuit and/ Or form communication equipment（For example, modem, communication switchboard, opto-electronic conversion equipment etc.）Circuit.This field it is common Technical staff it should be appreciated that theme as described herein can in a manner of analog or digital or combination thereof realize.

Referring additionally to Fig. 3 B, in il-lustrative example, circuit 302 and/or circuit 304 can be embodied in computing system 306（It is referred to as master computer or system）.In exemplary embodiments, by central processing unit（“CPU”）（Or microprocessor Device）308 are connected with system bus 310.Random access memory（“RAM”）312 couple with system bus 310, make CPU 308 can To access memory storage 314（It is associated with one or more parameters of nuclear fission traveling wave burnfront 22 to can be used for storage Data）.When the programming instructions are executed, those processing steps are stored in RAM 312 by CPU 308, and in the outer of RAM 312 Face performs the processing step of storage.

Computing system 306 via network interface 316 and can pass through network connectivity（It is not shown）With computer network（Do not show Go out）Connection.A kind of such network is that computing system 306 is allow to download application program, code, file and other electronic information Internet.

Read-only memory（“ROM”）318 are provided as storage as enabled instruction sequence or basic input/output operations system （BIOS）Constant command sequence as sequence.

Input/output（“I/O”）Equipment interface 320 allows computing system 306 and various input-output apparatus, for example, Keyboard, positioning device（" mouse "）, monitor, printer, the connections such as modem.For simplicity, I/O equipment interfaces 320 are shown as single frame, but can include several interfaces with the handing-over of different types of I/O equipment.

It will be understood that, these embodiments are not limited to show the framework of computing system 306 in figure 3b.According to application/business The type of industry environment, computing system 306 can contain more or less components.For example, computing system 306 can be set-top box, Laptop computer, laptop, desktop system or other types of system.

In various embodiments, some parts of disclosed system and method include one or more computer programs productions Product.Computer program product is including the computer readable storage medium as non-volatile memory medium and is embodied in computer In readable storage medium storing program for executing, as series of computation machine instruct computer readable program code part.In general, computer program It is stored and executed as processing unit or associated storage device as describing processing component in figure 3b.

On this respect, Fig. 2A -2M and Fig. 3 A-3C are the method, system and program product according to various embodiments respectively Flow chart and block diagram.It is readily apparent that, the combination of the frame in each frame and flow chart and block diagram of flow chart and block diagram can lead to Cross computer program instructions realization.These computer program instructions can be loaded into computer or other programmable devices and be formed One machine realizes regulation in flow chart or block diagram so that the instruction performed on computer or other programmable devices is formed Function component.These computer program instructions, which can also be stored in, can instruct computer or other programmable devices with spy Determine in the computer-readable memory that mode works, include in fact so that the instruction being stored in computer-readable memory becomes Now provide the article of the command device of the function in flow chart or block diagram.Computer program instructions can also be loaded into computer Or it is formed the series of operation steps to be performed on computer or other programmable devices in other programmable devices and calculated Machine realizes process, realizes regulation in flow chart or block diagram so that the instruction performed on computer or other programmable devices provides In function the step of.

Then, the frame of flow chart or block diagram is supported to perform the combination of the component of predetermined function, performs the step of predetermined function Combination and perform predetermined function program instruction means.It will be understood that each frame and flow chart of flow chart or block diagram or The combination of frame in block diagram can by perform predetermined function or step based on specialized hardware computer system or specialized hardware It is realized with the assembly of computer instruction.

Referring additionally to Fig. 3 C, in some embodiments, further circuit 304 can be configured to determine the combustion of nuclear fission traveling wave Burn the existing shape of front 22.For example, sensor 322 can be via with being properly entered 324 signal communication of interface can with circuit 304 Operation coupling.Sensor 322 can include any proper sensors of the parameter of measurement nuclear fission traveling wave burnfront 324.Example Such as, sensor 322 can measure neutron flux, neutron fluence, burnup, and/or reactivity（Or their any ingredient）.

As discussed above, it can be configured to and provide the embodiment of system 300 and circuit 302 and 304 to the side of execution Method 200（Fig. 2A -2M）Appropriate system environments, be loaded into spite of by program instruction in computer or other programmable devices A machine is formed, realizes regulation in flow chart or frame so that the instruction performed on computer or other programmable devices is formed The combination of the device and the frame in flow chart or block diagram of function passes through specified in figure or each frame of flow chart or block diagram The assembly based on specialized hardware computer system or specialized hardware and computer instruction of predetermined function or step is performed come real It is existing.Some features of the embodiment of system 300 will be discussed referring additionally to Figure 1B -1D, 1J, 1L, 1O, 1Q, 1R-1W and 2A-2M.

For this purpose, in some embodiments, further circuit 304 can be configured in a manner of shape desired by foundation, Determine selected several moving from respective first position to the respective second position along the first dimension of fission fuel subassembly 14 It moves.Further circuit 304 can be configured in a manner of shape desired by holding, determine the institute of fission fuel subassembly 14 Select several migrations along the first dimension from respective first position to the respective second position.Further circuit 304 can be configured Into in a manner of shape desired by response, determine that migrating core along the first dimension from respective first position to the respective second position splits Become selected several time of fuel subassembly 14.

As discussed above, in some embodiments, fission fuel subassembly 14 can be extended along the second dimension.

In addition as discussed above, in some embodiments, the first dimension can almost with fission fuel subassembly 14 The axis of elongation it is orthogonal.First dimension and the second dimension can be almost mutually orthogonal.

In various embodiments, the first dimension can include radial dimension, and the second dimension can include axial dimension；The Dimension can include axial dimension, and the second dimension can include radial dimension；First dimension can include axial dimension, and Second dimension can include transverse dimensions；And/or first dimension can include transverse dimensions, and the second dimension can include it is axial Dimension.

In some embodiments, first position, which can include outer position 30 and the second position, can include inner position 32.As desired, inner position 32 and outer position 30 can be without limitation as based on the central parts with reactor core 12 Point geometry proximity, the neutron that the neutron flux on inner position 32 is more than on outer position 30 is caused based on neutron flux to lead to It measures, and/or the k on inner position 32 is caused based on reactivity_effectiveMore than the k on outer position 30_effectiveIt is based on like that Each attribute.

In some other embodiments, first position, which can include inner position 32 and the second position, can include outside Position 30.As desired, inner position 32 and outer position 30 can without limitation as based on in reactor core 12 The geometry proximity of center portion point, in causing that the neutron flux on inner position 32 is more than on outer position 30 based on neutron flux Sub- flux, and/or based on reactivity so that inner position 32 on k_effectiveMore than the k on outer position 30_effectiveLike that Based on each attribute.In some embodiments, first position and the second position can be in the phase of reference value along the first dimension On offside.

In some other embodiments, first position and the second position can include substantially balanced at least one attribute. For example, at least one attribute can include with the geometry proximity of the central part of reactor core 12, neutron flux, and/or Reactivity.

In some embodiments, further circuit 304 can be configured to determine selected by fission fuel subassembly 14 Several at least one rotations.In some other embodiments, further circuit 304 can be configured to determine nuclear fission combustion Expect the selected several at least one reverse of subassembly 14.

As discussed above, in some embodiments, selected group of dimension constraint can be included along the pre- of the second dimension Determine maximum range.

In some other embodiments, selected group of dimension constraint can be the function of at least one burnfront criterion. For example, burnfront criterion can include without limitation：Several at least one as selected by with fission fuel subassembly 14 Neutron flux as a associated neutron flux；Several at least one phase as selected by with fission fuel subassembly 14 Neutron fluence as associated neutron fluence；It is and/or several at least one as selected by with fission fuel subassembly 14 Burnup as associated burnup.In some embodiments, burnfront criterion can include fission fuel subassembly 14 It is selected it is several it is at least one in burnfront position.

In some embodiments, further circuit 304 can be configured to determine selected by fission fuel subassembly 14 Several radial migrations along the first dimension from respective first position to the respective second position.Further circuit 304 can be matched somebody with somebody It is set to the selected several along the first dimension from respective first position to the respective second position of definite fission fuel subassembly 14 Spiral migration.Further circuit 304 can be configured to determine several along first selected by fission fuel subassembly 14 Axial translation of the dimension from respective first position to the respective second position.

In some embodiments, further circuit 302 can be configured to determine the big of nuclear fission traveling wave burnfront 22 It causes spherical.Circuit 302 further can be configured to determine to the continuous bend surface shape of nuclear fission traveling wave burnfront 22.

In various embodiments, the desired shape of nuclear fission traveling wave burnfront 22 can surround the second dimension substantially Rotational symmetry；There can be the substantially n fold rotational symmetry around the second dimension；It and/or can be non-limitingly as enclosing It is asymmetrical as the second dimension rotation asymmetry.

For for another example and referring now to Fig. 4 A, another illustrative system 400 is for migration nuclear fission combustion Expect subassembly（It is not shown in Fig. 4 A）And provide.It is provided by nonrestrictive example, system 400 can provide the side of execution Method 100（Figure 1A -1AF）Appropriate system environments.In this way, make following discussion referring additionally to Figure 1A -1AF.

In some embodiments, for the nuclear fission traveling wave burnfront 22 propagated along the first and second dimensions, by electricity Road 402 is configured to constrain along the second dimension according to selected group of dimension in fission fuel subassembly 14, determines nuclear fission The desired shape of traveling wave burnfront 22.Circuit 404 is configured in a manner of shape desired by response, determines that nuclear fission is fired Expect selected several migrations along the first dimension from respective first position to the respective second position of subassembly 14.By subassembly 405, which are configured to respond to circuit 404, migrates the selected several of fission fuel subassembly 14.

It will be understood that, circuit 402 and 404 can be similar to circuit 302 and 304.In some cases, circuit 402 and 404 can With identical with circuit 302 and 304.For this purpose, for simplicity, without repeating those details to understand.

It, can be specific by circuit 402 and/or circuit 404 in il-lustrative example as general introduction and referring additionally to Fig. 4 B It is melted into computing system 406（It is referred to as master computer or system）.In exemplary embodiments, by central processing unit （“CPU”）（Or microprocessor）408 are connected with system bus 410.Random access memory（“RAM”）412 with system bus 410 Coupling, allows CPU 408 to access memory storage 414（It can be used for one of storage and nuclear fission traveling wave burnfront 22 Or the associated data of multiple parameters）.When the programming instructions are executed, those processing steps are stored in RAM412 by CPU 408, And perform the processing step of storage in the outside of RAM 412.Computing system 406 via network interface 416 and can pass through network Line（It is not shown）With computer network（It is not shown）Connection.Read-only memory（“ROM”）418 are provided as storage refers to as starting Make sequence or basic input/output operations system（BIOS）Constant command sequence as sequence.Input/output（“I/O”）If Standby interface 420 allows computing system 406 and various input-output apparatus, for example, keyboard, sensing equipment（" mouse "）, monitoring The connections such as device, printer, modem.It will be understood that, these embodiments are not limited to show computing system 406 in figure 4b Framework.Computing system 306 is directed to without limitation（Fig. 3 B）Discussion can also be applied to computing system 406.

In various embodiments, some parts of disclosed system and method include one or more computer programs productions Product.Above for system 300（Fig. 3 A）The discussion of related computer program product can also be applied to system 400.

On this respect, Figure 1A, 1I, 1K, 1M-1N, 1P and 1X-1AF and Fig. 4 A-4C are according to various implementations respectively The method of example, the flow chart and block diagram of system and program product.It should be understood that each frame and flow of flow chart and block diagram The combination of frame in figure and block diagram can be realized by computer program instructions.These computer program instructions can be loaded into meter A machine is formed in calculation machine or other programmable devices, so as to the instruction shape performed on computer or other programmable devices Into the component for realizing function of the regulation in flow chart or block diagram.These computer program instructions, which can also be stored in, to be instructed It, can be stored in computer in the computer-readable memory that computer or other programmable devices work in a specific way Reading the instruction in memory becomes the article for the command device for including realizing function of the regulation in flow chart or block diagram.Computer Program instruction, which can also be loaded into computer or other programmable devices, to be made to hold on computer or other programmable devices Capable series of operation steps forms computer and realizes process, so as to the instruction performed on computer or other programmable devices It provides and realizes the step of providing the function in flow chart or block diagram.

Then, the frame of flow chart or block diagram is supported to perform the combination of the device of predetermined function, performs the step of predetermined function Combination and perform predetermined function program instruction means.It should also be understood that each frame and flow chart of flow chart or block diagram Or the combination of the frame in block diagram can by perform predetermined function or step based on specialized hardware computer system or special hard The assembly of part and computer instruction is realized.

Referring additionally to Fig. 4 C, in some embodiments, further circuit 404 can be configured to determine the combustion of nuclear fission traveling wave Burn the existing shape of front 22.For example, sensor 422 can be via with being properly entered 324 signal communication of interface can with circuit 404 Operation coupling.Circuit 404, sensor 422 and input interface 424 can be with circuit 304, sensor 322 and input interfaces 324 （Fig. 3 C）It is similar（It in some cases, can be identical）.Here their details is repeated it is unnecessary to understand.

As discussed above, the embodiment of system 400, circuit 402 and 404 and subassembly 405 can be configured to Execution method 100 is independently provided as follows（Figure 1A, 1I, 1K, 1M-1N, 1P and 1X-1AF）Appropriate system environments：Program is referred to Order is loaded into one machine of formation in computer or other programmable devices, to be held on computer or other programmable devices Capable instruction forms the device for realizing function of the regulation in each frame of flow chart or block diagram or flow chart or block diagram, and flows The combination of the frame of journey figure or block diagram by perform predetermined function or step based on specialized hardware computer system or specialized hardware It is realized with the assembly of computer instruction.Some features of the embodiment of system 400 will be discussed referring additionally to Figure 1A -1AF.

In some embodiments and with reference to Fig. 4 C, further circuit 404 can be configured to determine the combustion of nuclear fission traveling wave Burn the existing shape of front 22.It is such determine can be with as described above, circuit 304（Fig. 3 A）Similar or identical mode make Go out.For this purpose, sensor 422 and input interface 424 can be with sensors 322 and input interface 324（Fig. 3 C）It is similar or at some In the case of it is identical.Sensor 422, input interface 424 and circuit 404 are such as above for sensor 322,324 and of input interface Circuit 304（Fig. 3 C）Cooperation as discussing.

In some embodiments, further circuit 404 can be configured in a manner of shape desired by foundation, determine core Selected several migrations along the first dimension from respective first position to the respective second position of fission fuel subassembly 14.One In a little other embodiments, further circuit 404 can be configured in a manner of shape desired by holding, to determine fission fuel Selected several migrations along the first dimension from respective first position to the respective second position of subassembly 14.

In some embodiments, further circuit 404 can be configured in a manner of shape desired by response, determine edge It the first dimension and the time several selected by fission fuel subassembly 14 is migrated from respective first position to the respective second position.

In some embodiments, fission fuel subassembly 14 can be extended along the second dimension.First dimension can be several It is orthogonal with the axis of elongation of fission fuel subassembly 14.First dimension and the second dimension can be almost mutually orthogonal.

In some embodiments, first position, which can include outer position 30 and the second position, can include inner position 32.Inner position 32 and outer position 30 can be based on：With the geometry proximity of the central part of reactor core 12；Neutron leads to Amount is so that the neutron flux on inner position 32 is more than the neutron flux on outer position 30；And/or reactivity is so that the inside position Put the k on 32_effectiveMore than the k on outer position 30_effective。

In some other embodiments, first position, which can include inner position 32 and the second position, can include outside Position 30.Inner position and outer position can the geometry proximities based on the central part with reactor core 12；In being based on Sub- flux causes the neutron flux on inner position 32 to be more than the neutron flux on outer position 30；And/or made based on reactivity Obtain the k on inner position 32_effectiveMore than the k on outer position 30_effective。

In some embodiments, first position and the second position can be in the opposite side of reference value along the first dimension On.

In some other embodiments, first position and the second position can include substantially balanced at least one attribute. For example, at least one attribute can include the geometry proximity with the central area of reactor core 12；Neutron flux；And/or Reactivity.

In various embodiments, further circuit 404 can be configured to determine selected by fission fuel subassembly 14 Several at least one rotations.Further circuit 404 can be configured to determine several selected by fission fuel subassembly 14 It is a at least one reverse.

Subassembly 405 can include without limitation as reactor core kernel fuel-management device, in the prior art Any appropriate nuclear fuel management device known.But in some other embodiments, subassembly 405 can include reactor core outer core Fuel-management device.

It is unrelated with the form for embodying subassembly 405, in various embodiments, further subassembly 405 can be matched somebody with somebody It is set to from several selected by respective first position to respective second position radial migration fission fuel subassembly 14.It can be into one Subassembly 405 is configured to migrate the institute of fission fuel subassembly 14 from respective first position to respective second position spiral by step It selects several.Further subassembly 405 can be configured to several selected by axial translation fission fuel subassembly 14.

In some embodiments, subassembly 405 can be further configured to the institute of rotation fission fuel subassembly 14 It selects several.In some other embodiments, can subassembly 405 be further configured to reverse fission fuel subassembly 14 It is selected several.Referring now to Fig. 5, in various embodiments, illustrative nuclear fission traveling wave reactor 500 can be provided.Nuclear fission Traveling wave reactor 500 includes nuclear fission traveling wave reactor core 12.As discussed above, in nuclear fission traveling wave reactor core 12 Middle receiving fission fuel subassembly 14.Each fission fuel subassembly 14 is configured to make nuclear fission traveling wave burnfront 22 It is propagated wherein along the first and second dimensions.Circuit 402 is configured in fission fuel subassembly 14 according to selected group Dimension constraint along the second dimension, determine the desired shape of nuclear fission traveling wave burnfront 22.By circuit 404 be configured to The mode of shape desired by response determines, fission fuel subassembly 14 it is selected several along the first dimension from respective first Put the migration to the respective second position.Subassembly 405 is configured to respond to circuit 404, migration fission fuel subassembly 14 It is selected several.

Therefore, reactor 500 can be embodied in system 400 discussed above combined and cooperated also as above The reactor core 12 discussed.Because reactor core 12 has been directed to above（And its component）With system 400（And its portion Part）Details is given, so without repeating details to understand.

As having been discussed above, in various embodiments, further circuit 404 can be configured to determine The existing shape of nuclear fission traveling wave burnfront 22.Further circuit 404 can be configured to the side of shape desired by foundation Formula determines the selected several along the first dimension from respective first position to the respective second position of fission fuel subassembly 14 Migration.Further circuit 404 can be configured in a manner of shape desired by maintenance, determine fission fuel subassembly 14 Selected several migrations along the first dimension from respective first position to the respective second position.

As discussed above, in some embodiments, further circuit 404 can be configured to respond desired shape Mode, determine to migrate the institute of fission fuel subassembly 14 along the first dimension from respective first position to the respective second position Select several time.

In some embodiments, fission fuel subassembly 14 can be extended along the second dimension.

In some embodiments, the first dimension can be almost orthogonal with the axis of elongation of fission fuel subassembly 14.One In a little embodiments, the first dimension and the second dimension can be almost mutually orthogonal.

In some embodiments, first position, which can include outer position 30 and the second position, can include inner position 32.Inner position 32 and outer position 30 can the geometry proximities based on the central part with reactor core 12；Neutron leads to Amount is so that the neutron flux on inner position 32 is more than the neutron flux on outer position 30；And/or reactivity is so that the inside position Put the k on 32_effectiveMore than the k on outer position 30_effective。

In some other embodiments, first position, which can include inner position 32 and the second position, can include outside Position 30.Inner position 32 and outer position 30 can the geometry proximities based on the central part with reactor core 12；In Sub- flux causes the neutron flux on inner position 32 to be more than the neutron flux on outer position 30；And/or in reactivity causes K on face position 32_effectiveMore than the k on outer position 30_effective。

In various embodiments and as discussed above, further circuit 404 can be configured to determine nuclear fission combustion Expect selected several at least one rotation of subassembly 14 and/or be further configured to determine fission fuel subassembly 14 It is selected several at least one reverse.

In some embodiments, selected group of dimension constraint can include the predetermined maximal distance along the second dimension. In some other embodiments, selected group of dimension constraint can be non-limitingly as at least one burnfront as following The function of criterion：In several at least one associated neutron flux as selected by with fission fuel subassembly 14 Sub- flux；Neutron several at least one associated neutron fluence as selected by with fission fuel subassembly 14 is noted Amount；And/or burnup several at least one associated burnup as selected by with fission fuel subassembly 14.One In a little other embodiments, burnfront criterion can include fission fuel subassembly 14 it is selected it is several it is at least one in Burnfront position.

In various embodiments, further circuit 404 can be configured to determine selected by fission fuel subassembly 14 Several radial migrations along the first dimension from respective first position to the respective second position.Further circuit 404 can be matched somebody with somebody It is set to the selected several along the first dimension from respective first position to the respective second position of definite fission fuel subassembly 14 Spiral migration.Further circuit 404 can be configured to determine that axial direction several selected by fission fuel subassembly 14 is put down It moves,

In various embodiments, further circuit 402 can be configured to determine the big of nuclear fission traveling wave burnfront 22 Cause spherical, and/or nuclear fission traveling wave burnfront 22 continuous bend surface shape.Nuclear fission traveling wave burnfront 22 is wished Hope that shape can surround the second dimension substantially rotational symmetry；There can be the substantially n fold rotational symmetry around the second dimension Property；And/or can be asymmetrical as asymmetric around the rotation of the second dimension.

In some embodiments, subassembly 405 can include nuclear fuel management device.As discussed above, subassembly 405 It can include without limitation as reactor core kernel fuel-management device, any appropriate nuclear fuel known in the prior art Managing device.But in some other embodiments, subassembly 405 can include reactor core outer core fuel-management device.

In addition as discussed above, in various embodiments, further subassembly 405 can be configured to from respective first It is several selected by position to respective second position radial migration fission fuel subassembly 14.It can be further by subassembly 405 It is configured to migrate from respective first position to respective second position spiral several selected by fission fuel subassembly 14.It can be into Subassembly 405 is configured to several selected by axial translation fission fuel subassembly 14 by one step.It can be further by subassembly 405 are configured to the selected several of rotation fission fuel subassembly 14.Can subassembly 405 further be configured to reverse core to split Become the selected several of fuel subassembly 14.

Referring now to Fig. 6 A, in some embodiments, the method 600 of operation nuclear fission traveling wave reactor is provided.Method 600 since frame 602.Referring additionally to Figure 1B, in block 604, by least one fission fuel subassembly 14 from nuclear fission row First position in ripple reactor core 12 outwards moves to the second position in nuclear fission traveling wave reactor core 12.In frame Terminate this method 600 in 606.

In some embodiments and referring additionally to Fig. 6 B, in block 608, at least one can be inwardly migrated from the second position A fission fuel subassembly 14.

In various embodiments, first position and the second position can be based on the several of the central part with reactor core 12 What proximity；Based on neutron flux so that the neutron flux on first position is more than the neutron flux on the second position；And/or base Cause the k on first position in reactivity_effectiveMore than the k on the second position_effective。

Referring now to Fig. 7, in some embodiments, the method 700 of operation nuclear fission traveling wave reactor is provided.Method 700 since frame 702.Referring additionally to Figure 1B, in block 704, at least one fission fuel subassembly 14 is determined, in first party To from the first position in nuclear fission traveling wave reactor core 12 to the second position in nuclear fission traveling wave reactor core 12 Migration.The second position is different from first position.In frame 706, determine at least one fission fuel subassembly 14 in second party To the migration from the second position.Second direction is different from first direction.Terminate this method 700 in frame 708.

In some embodiments, first direction can be outside, and second direction can be inside.First position and the second position It can be based on without limitation as attribute as following or parameter：It is approached with the geometry of the central part of reactor core 12 Property；Neutron flux causes the neutron flux on first position to be more than the neutron flux on the second position；And/or reactivity is so that the K on one position_effectiveMore than the k on the second position_effective。

In some embodiments, first direction can be inside, and second direction can be outside.The second position and first position It can be based on without limitation as attribute as following or parameter：It is approached with the geometry of the central part of reactor core 12 Property；Neutron flux causes the neutron flux on the second position to be more than the neutron flux on first position；And/or reactivity is so that the K on two positions_effectiveMore than the k on first position_effective。

Referring now to Fig. 8, in some embodiments, the method 800 of operation nuclear fission traveling wave reactor is provided.Method 800 since frame 802.Referring additionally to Figure 1B, in frame 804, by least one fission fuel subassembly 14, in a first direction The second position in nuclear fission traveling wave reactor core 12 is moved to from the first position in nuclear fission traveling wave reactor core 12. The second position is different from first position.In frame 806, determine at least one fission fuel subassembly 14 in second direction from The migration of two positions.Second direction is different from first direction.Terminate this method 800 in block 808.

Referring now to Fig. 9, in some embodiments, the method 900 of operation nuclear fission traveling wave reactor is provided.Method 900 since frame 902.Referring additionally to Figure 1B, in frame 904, by least one fission fuel subassembly 14, in a first direction The second position in nuclear fission traveling wave reactor core 12 is moved to from the first position in nuclear fission traveling wave reactor core 12. The second position is different from first position.In frame 906, at least one fission fuel point is migrated from the second position in second direction Component 14.Second direction is different from first direction.Terminate this method 900 in frame 908.

Referring now to Figure 10 A, in some embodiments, the method 1000 of operation nuclear fission traveling wave reactor is provided.Side Method 1000 is since frame 1002.In frame 1004, predetermined burn up level is selected.In frame 1006, in nearly all nuclear fission All reach the mode of the burn up level equal to predetermined burn up level in fuel assembly, determine that the core in fission-type reactor reactor core is split Become selected several migration of fuel assembly.Terminate this method 1000 in frame 1008.

Referring additionally to Figure 10 B, in some embodiments, in frame 1010, can be moved in a manner that response determines migration Move the selected several of the fission fuel assemblies in fission-type reactor reactor core.

Referring additionally to Figure 10 C, in some embodiments, in frame 1012, when burn up level is equal to predetermined burn up level, It can determine respective selected several removals of fission fuel assemblies.

Referring additionally to Figure 10 D, in some embodiments, in frame 1014, identified removal is responded, core can be removed and split Become the selected several of fuel assembly.

For the sake of showing for clarity, the application has used formal generality title.It should be appreciated, however, that these Generality title can discuss different types of theme for the purpose of displaying in entire application（For example, can process/ Equipment/structure is described under operation title and/or process/operation can be discussed under structure/prelude；And/or single topic Description can cross over two or more topic titles）.Therefore, the use of formal generality title is never intended to limit The scope of the present invention processed.

Those of ordinary skill in the art will be understood that particular exemplary process, equipment and/or technology above represent picture and exist With other places in the claims submitted herein and/or in the application like that, in more one told about elsewhere herein As process, equipment and/or technology.

It is appreciated by those skilled in the art that the prior art have advanced to system various aspects it is hard Almost without the stage of what difference between part, software and/or firmware realization；The use of hardware, software and/or firmware is general （But may not, because in some contexts, making a choice between hardware and software still significant）It is to represent in cost and effect The design alternative weighed between rate.Those of ordinary skill in the art will be understood that, process as described herein can be realized, be by existing The various instruments of system and/or other technologies（For example, hardware, software and/or firmware）, and preferred kit with deployment process, be System and/or other technologies background and become.For example, if implementor determines speed and precision is vital, implementor It can select main hardware and/or firmware vehicle；On the other hand, if flexibility is vital, implementor can select Select main software realization；Alternatively, in another aspect, implementor can select certain assembly of hardware, software and/or firmware.Cause , there are several possible instruments that can realize process as described herein, equipment and/or other technologies, without a kind of instrument day in this It is born with better than other instruments, because any instrument to be utilized all is to depend on any deployment tool that may all change Background and the special attention of implementor（For example, speed, flexibility or predictable）Option.Those of ordinary skill in the art It should be appreciated that the commonly used hardware related with optics of optics aspect, software and/or the firmware realized.

In some embodiments as described herein, logic and similar realize can include software or other control structures.Electricity Road can be contained, for example, one or more path of the electric current for building and arranging for realization various functions as described herein. In some implementations, one or more media can be configured to preserve or send when such medium rise as described herein The equipment of execution effect undertakes equipment when can detect instruction and can detect realization.In some variants, for example, some realizations can wrap It includes reception or transmission as being instructed by carrying out one or more related with one or many operations as described herein, more New or the existing software or firmware of modification, OR gate array or programmable hardware.Alternately or in addition, in some variants, one Kind, which is realized, can include special-purpose software, software, firmware component, and/or execution or otherwise call the universal component of special-purpose member. Some specifications or other realizations optionally, can be led to by one or more examples of tangible transmission media as described herein Cross grouping transmission or otherwise by being transmitted in the various times by distributed medium.

Alternately or in addition, some realizations can include performing special instruction sequence or call permission, triggering, association It adjusts, ask or otherwise cause the circuit of one or many generations of substantially any feature operation as described herein.In some changes In body, the operation of this paper or other logical descriptions can be expressed as source code and be compiled into executable instruction sequence or otherwise So called as executable instruction sequence.In some variants, for example, some realization can completely or partially by as C++ that The source code of sample or other code sequences provide.In other implementations, commercial product and/or in the prior art will can be used Various technologies source code or other codes realize compiling/realization/translate/be converted into high level description language（For example, it initially uses Technology described by the realization of C or C++ programming languages, being hereafter converted into programming language realization can the realization of logic synthetic language, hardware Description language realization, hardware design the Realization of Simulation, and/or other such similar expression ways）.For example, can by some or All logical expressions（For example, computer programming language is realized）It is expressed as Verilog type hardware descriptions（For example, it is retouched via hardware Predicate is sayed（HDL）And/or VHSIC hardware description language（VHDL））It can be used for creating after probable and contain hardware （For example, specific store circuit）Physics realization other circuit models.It will be appreciated by those skilled in the art that such as What is obtained according to these introductions, is configured and is optimized appropriate transmission or computing element, goods and materials, actuator or other structures.

Detailed descriptions above illustrates the various realities of equipment and/or process by using block diagram, flow chart and/or example Apply example.In the case where such block diagram, flow chart and/or example include one or more functions and/or operation, this field Those of ordinary skill should be understood that each function in such block diagram, flow chart or example and/or operation can be by more The various hardware of kind, software, firmware or their substantially any combination are individually and/or collective realizes.In one embodiment, originally Several parts of theme described in text can pass through application-specific integrated circuit（ASIC）, field programmable gate array（FPGA）, number Signal processor（DSP）Or other integrated forms are realized.But it is appreciated by those skilled in the art that herein The some aspects of disclosed embodiment can entirely or partly in integrated circuits equivalent implementation into operating in one or more One or more computer programs on computer（For example, it is implemented as operating in one in one or more computer systems Or multiple programs）, it is implemented as running one or more programs on the one or more processors（For example, it is implemented as operating in One or more programs in one or more microprocessors）, it is implemented as firmware or is implemented as their substantially any combination, And design circuit and/or for software and/or firmware write all complete one skilled in the relevant art of code technical ability it It is interior.In addition, those of ordinary skill in the art will be understood that, the mechanism of theme as described herein can be used as program product with a variety of Various form distribution and the exemplary embodiments of theme as described herein and signaling bearer Jie for being actually distributed The concrete type of matter is independently applied.The example of signal bearing medium includes but not limited to following medium：As floppy disk, hard drive Device, compact disc（CD）, digital video disc（DVD）, digital magnetic tape, recordable type medium as computer storage etc.；And As number and/or analogue communication medium（For example, Connectorized fiber optic cabling, waveguide, wired communications links, wireless communication link（For example, hair Penetrate machine, receiver, transmitting logic unit, reception logic unit etc.）Deng）Such transmission type media.

It is, in general, that it is appreciated by those skilled in the art that embodiment as described herein can be by various The Mechatronic Systems of type is individually and/or collective realizes, the Mechatronic Systems contain as hardware, software, firmware and/or they almost Any combination of varied electrical components；And as rigid body, elasticity or torsion body, hydraulic system, electromagnetically actuated equipment and/or it Substantially any combination can transfer varied component of mechanical force or movement like that.Therefore, as used throughout, " machine Electric system " include but not limited to operationally with energy converter（For example, actuator, motor, piezo-electric crystal, MEMS （MEMS）Deng）The circuit of coupling, the circuit containing at least one discrete circuit, contain the circuit containing at least one integrated circuit There is the circuit of at least one application-specific integrated circuit, form the universal computing device being made of computer program（For example, by least portion Divide the all-purpose computer or realized originally by least part that the computer program for realizing process and/or equipment as described herein is formed The microprocessor that the computer program of process and/or equipment described in text is formed）Circuit, formed storage device（It is for example, various Form（For example, arbitrary access, flash, read-only etc.）Memory）Circuit, formed communication equipment（For example, modem, Communication switchboard, opto-electronic conversion equipment etc.）Circuit, and/or any non-electrical analog as light or other analogs.This The those of ordinary skill in field will also be understood that the example of electric system includes but not limited to miscellaneous consumer electronics system System, Medical Devices and as motorized transport systems, factory automation system, security system, and/or communication/computing system Other systems.It is appreciated by those skilled in the art that as used herein Mechatronic Systems is not necessarily limited to have There is the system of electric actuation and mechanically actuated the two, unless otherwise indicated by context.

It is related with this specification and/or be listed in any application data form the upper surface of all United States Patent (USP)s, United States Patent (USP) Shen It please announce, U.S. Patent application, foreign patent, foreign patent application and non-patent announcement are all with degree not inconsistent with this paper It is herein incorporated by reference.

It is appreciated by those skilled in the art that elements illustrated herein（For example, operation）, equipment, object and It is used as the example of clarification concept with their discussion, it can be envisaged that go out various configuration modifications.Therefore, as used herein, open up The specific examples and adjoint discussion shown are intended to represent their more typically classification.It is, in general, that any specific examples make With being intended to the classification and particular elements that represent it（For example, operation）, equipment and object do not include should not be viewed as Restricted.

It can be on substantially any plural number used herein and/or singular references, those of ordinary skill in the art Plural number is proportionately changed into odd number and/or odd number is changed into plural number by context and/or application.For clarity, it is unknown herein Really show various singular/plural displacements.

Theme as described herein is sometimes illustrated in other different components or connected not from other different components Same component.It should be understood that the framework so described was merely an illustrative, it is in fact possible to realize many realization identical functions Other frameworks.From concept, effectively any arrangement of the component of " association " realization identical function, is wished to realize Hope function.Therefore, combine herein and realize that any two component of specific function is considered as mutual " association " so that with Framework or intermediate member independently realize desired function.Equally, so associated any two component can also be regarded as realizing Mutual " being operably connected " of desired function or " being operatively coupled " and being capable of so associated any two component It can also be regarded as realizing mutual " operably coupled " of desired function.Operably coupled special case includes but not limited to physically It can match and/or the component that physically interacts, can wirelessly interact and/or the component, and/or in logic of wirelessly interacting Interaction and/or/can interact component in logic.

Although the particular aspects of current topic as described herein have been shown and described, for the common skill of this field For art personnel, it is therefore apparent that can be made according to teaching herein without departing from theme as described herein and its broader aspect Go out change and modification, therefore, the appended claims by as the true spirit in theme as described herein and within the scope of It is all it is such change and modification be included within the scope of it.It will be understood by those skilled in the art that it is, in general, that It is used herein, it is used especially in described claims（For example, the major part of the appended claims）In term it is general It is intended as open to the outside world term（For example, gerund term " comprising " is construed as gerund " including but not limited to ", gerund Term " containing " is construed as gerund " at least containing ", verb term " comprising " be construed as verb " including but it is unlimited In " etc.）.Those of ordinary skill in the art should also be understood that if there is expectation shows certain amount of introduced claim row Item is lifted, then will clearly enumerate such intention in the claims, and in the case where being enumerated as shortage, then there is no this The intention of sample.For example, it is appreciated that, following the appended claims may be included using introductory phrase " at least in order to help One " and " one or more " introduce claim recitation item.But even if same claim includes introductory phrase " one or more " or " at least one " and as "one" or " one kind "（For example, "one" and/or " one kind " should usually manage Solution is into " at least one " or the meaning of " one or more "）Such indefinite article, the use of such phrase also should not be understood Claim is so introduced to imply to introduce claim recitation item by indefinite article "one" or " one kind " and will include Any specific rights requirement of listed item is limited in the claim only comprising such listed item；For being used to introduce power Profit requires the use of the definite article of listed item, this similary establishment.In addition, even if clearly list certain amount of introduced right It is required that listed item, those of ordinary skill in the art are it should also be appreciated that such enumerate is generally understood that at least have The meaning of cited quantity（For example, in the case of no other qualifiers, only enumerate " two listed items " generally mean that Few two listed items or two or more listed items）.Moreover, using the habit similar to " A, B and C's etc. is at least one " In the case of usage, it is, in general, that such structure, which is intended to those of ordinary skill in the art, understands the usage In the sense that use（For example, " at least one system containing A, B and C " will include but not limited to contain only A, B is contained only, C is contained only, together containing A and B, together containing A and C, the system containing B and C and/or together containing A, B and C etc. together）. In the case of the usage similar to " A, B or C's etc. is at least one " is used, it is, in general, that such structure purport One skilled in the relevant art uses in the sense that understanding the usage（For example, " contain at least one of A, B or C System " will include but not limited to contain only A, contain only B, contain only C, together containing A and B, together containing A and C, contain together There are B and C and/or the system together containing A, B and C etc.）.Those of ordinary skill in the art should also be understood that in general, no matter In description, claims or attached drawing, the separation word of two or more alternative projects and/or phrase occur should manage Solution into including one of these projects, say unless the context otherwise by the possibility of any one or two projects of these projects It is bright.For example, phrase " A or B " is usually understood as including " A ", the possibility of " B " or " A and B ".

On the appended claims, those of ordinary skill in the art will be understood that, operation cited herein generally may be used To be performed in any order.In addition, although various operating processes are shown in order, it is to be understood that, various operations can be with It is performed or may be performed simultaneously by the other order different from illustrated order.The example of so alternative sequence can be with Including being overlapped, interlocking, blocking, resetting, incremental, prepared, supplement, simultaneously, reversely or other derivative sequences, unless context is another It is described.Moreover, as " response ... ", " with ... it is related " or other past tense adjectives term be generally not intended to repel this The derivative of sample, unless otherwise indicated by context.

The some aspects of theme as described herein are shown with following number provision:

1. a kind of method for operating nuclear fission traveling wave reactor, the method include：

In multiple fission fuel subassemblies in the reactor core of nuclear fission traveling wave reactor, make nuclear fission traveling wave Burnfront is propagated along the first and second dimensions；And

In a manner of limiting the shape of nuclear fission traveling wave burnfront along the second dimension according to the constraint of selected group of dimension, It is controllably migrated along the first dimension from respective first position to the respective second position several selected by multiple fission fuel subassemblies It is a.

2. the method as described in provision 1, plurality of fission fuel subassembly is extended along the second dimension.

3. the method as described in provision 1, wherein the first dimension almost with the axis of elongation of multiple fission fuel subassemblies just It hands over.

4. the method as described in provision 1, wherein the first dimension and the second dimension are almost mutually orthogonal.

5. the method as described in provision 1, wherein：

First dimension includes radial dimension；And

Second dimension includes axial dimension.

6. the method as described in provision 1, wherein：

First dimension includes axial dimension；And

Second dimension includes radial dimension.

7. the method as described in provision 1, wherein：

First dimension includes axial dimension；And

Second dimension includes transverse dimensions.

8. the method as described in provision 1, wherein：

First dimension includes transverse dimensions；And

Second dimension includes axial dimension.

9. the method as described in provision 1, wherein：

First position includes outer position；And

The second position includes inner position.

10. the method as described in provision 9, wherein inner position and outer position are based on the central part with reactor core Geometry proximity.

11. the method as described in provision 9, wherein inner position and outer position are based on neutron flux so that inner position On neutron flux be more than outer position on neutron flux.

12. the method as described in provision 9, wherein inner position and outer position are based on reactivity so that on inner position K_effectiveMore than the k on outer position_effective。

13. the method as described in provision 1, wherein：

First position includes inner position；And

The second position includes outer position.

14. the method as described in provision 13, wherein inner position and outer position are based on the central part with reactor core The geometry proximity divided.

15. the method as described in provision 13, wherein inner position and outer position are based on neutron flux so that inner position On neutron flux be more than outer position on neutron flux.

16. the method as described in provision 13, wherein inner position and outer position are based on reactivity so that on inner position K_effectiveMore than the k on outer position_effective。

17. the method as described in provision 1, wherein first position and the second position are in the phase of reference value along the first dimension On offside.

18. the method as described in provision 1, wherein first position and the second position include substantially balanced at least one category Property.

19. the method as described in provision 18, wherein at least one attribute includes several with the central area of reactor core What proximity.

20. the method as described in provision 18, wherein at least one attribute includes neutron flux.

21. the method as described in provision 18, wherein at least one attribute includes reactivity.

22. the method as described in provision 1, wherein along the first dimension from respective first position to the respective second position, it can Control migrates the selected several including rotating the selected several of multiple fission fuel subassemblies of multiple fission fuel subassemblies It is at least one.

23. the method as described in provision 1, wherein along the first dimension from respective first position to the respective second position, it can Control migrates the selected several including overturning the selected several of multiple fission fuel subassemblies of multiple fission fuel subassemblies It is at least one.

24. the method as described in provision 1, wherein selected group of dimension constraint include along the second dimension it is predetermined it is maximum away from From.

25. the method as described in provision 1, wherein selected group of dimension constraint is the letter of at least one burnfront criterion Number.

26. the method as described in provision 25, wherein burnfront criterion include neutron flux.

27. the method as described in provision 26, wherein will be several selected by neutron flux and multiple fission fuel subassemblies It is at least one associated.

28. the method as described in provision 25, wherein burnfront criterion include neutron fluence.

29. the method as described in provision 28, wherein will be several selected by neutron fluence and multiple fission fuel subassemblies It is at least one associated.

30. the method as described in provision 25, wherein burnfront criterion include burnup.

31. the method as described in provision 30, wherein by selected by burnup and multiple fission fuel subassemblies it is several extremely Few one associated.

32. the method as described in provision 25, wherein burnfront criterion include the selected of multiple fission fuel subassemblies Several at least one interior burnfront positions.

33. the method as described in provision 1, wherein controllable from respective first position to the respective second position along the first dimension Migrate multiple fission fuel subassemblies it is selected it is several including：Along the first dimension from respective first position to respective second It puts and radially controllably migrates the selected several of multiple fission fuel subassemblies.

34. the method as described in provision 1, wherein controllable from respective first position to the respective second position along the first dimension Migrate multiple fission fuel subassemblies it is selected it is several including：Along the first dimension from respective first position to respective second It puts and spirally controllably migrates the selected several of multiple fission fuel subassemblies.

35. the method as described in provision 1, wherein controllable from respective first position to the respective second position along the first dimension Migrate multiple fission fuel subassemblies it is selected it is several including：Along the first dimension from respective first position to respective second It puts and axially controllably migrates the selected several of multiple fission fuel subassemblies.

36. the method as described in provision 1, the shape of wherein nuclear fission traveling wave burnfront is approximately spherical.

37. the method as described in provision 1, the wherein shape of nuclear fission traveling wave burnfront and selected line curved surface are big Cause is consistent.

38. the method as described in provision 1, the shape of wherein nuclear fission traveling wave burnfront is substantially revolved around the second dimension Turn symmetrical.

39. the method as described in provision 1, the wherein shape of nuclear fission traveling wave burnfront have around the big of the second dimension Cause n fold rotational symmetry.

40. the method as described in provision 1, the shape of wherein nuclear fission traveling wave burnfront along the second dimension is asymmetric 's.

41. the method as described in provision 40, the shape of wherein nuclear fission traveling wave burnfront is rotated around the second dimension It is asymmetric.

42. the method as described in provision 1 further includes and triggers nuclear fission row using multiple nuclear fission traveling wave ignition modules Ripple burnfront.

43. the method as described in provision 42, it is further contained in along the first dimension from respective first position to respective Two positions controllably migrate multiple fission fuel subassemblies it is selected it is several before, remove multiple nuclear fission traveling wave ignition modules It is at least one.

44. the method as described in provision 43, wherein along the first dimension from respective first position to the respective second position Controllably migrate multiple fission fuel subassemblies it is selected it is several before, remove at least the one of multiple nuclear fission traveling wave ignition modules It is a including：Multiple fission fuel subassemblies are controllably being migrated along the first dimension from respective first position to the respective second position It is selected it is several before, at least one of multiple nuclear fission traveling wave ignition modules is removed from the second position.

45. the method as described in provision 1, further includes：Make nuclear fission traveling wave reactor along the first dimension from each Controllably migrated from first position to the respective second position it is several selected by multiple fission fuel subassemblies before, become Asia and face Boundary.

46. the method as described in provision 45, wherein nuclear fission traveling wave reactor is made to become subcritical including by neutron-absorbing In material intercalation reaction heap reactor core.

47. the method as described in provision 45, further includes：Along the first dimension from respective first position to respective Two positions controllably migrate multiple fission fuel subassemblies it is selected it is several after, re-establish critical.

48. the method as described in provision 47, wherein re-establish it is critical including：Neutron-absorbing is removed from reactor core At least part of material.

49. the method as described in provision 45, further includes：Along the first dimension from respective first position to respective Two positions controllably migrate multiple fission fuel subassemblies it is selected it is several before, close nuclear fission traveling wave reactor.

50. the method as described in provision 49, further includes：Along the first dimension from respective first position to respective Two positions controllably migrate multiple fission fuel subassemblies it is selected it is several after, restart nuclear fission traveling wave reactor.

51. a kind of method for controlling fission fuel reactor, the method include：

For the nuclear fission traveling wave burnfront propagated along the first and second dimensions, in multiple fission fuel subassemblies The interior dimension according to selected group constrains the desired shape for along the second dimension, determining nuclear fission traveling wave burnfront；And

In a manner of shape desired by response, the selected several along the first dimension of multiple fission fuel subassemblies are determined Migration from from respective first position to the respective second position.

52. the method as described in provision 51, further includes：

Determine the existing shape of nuclear fission traveling wave burnfront.

53. the method as described in provision 51 wherein in a manner of shape desired by response, determines multiple fission fuels point The selected of component several includes along the first dimension from respective first position to the migration of the respective second position：With desired by foundation The mode of shape, determine multiple fission fuel subassemblies it is selected it is several along the first dimension from respective first position to respective The migration of the second position.

54. the method as described in provision 51 wherein in a manner of shape desired by response, determines multiple fission fuels point The selected of component several includes along the first dimension from respective first position to the migration of the respective second position：With desired by maintenance The mode of shape, determine multiple fission fuel subassemblies it is selected it is several along the first dimension from respective first position to respective The migration of the second position.

55. the method as described in provision 51, further includes：

In a manner of shape desired by response, determine to move from respective first position to the respective second position along the first dimension Move selected several time of multiple fission fuel subassemblies.

56. the method as described in provision 51, further includes：

In a manner of shape desired by response, migrated along the first dimension from respective first position to the respective second position more A fission fuel subassembly it is selected several.

57. the method as described in provision 51, plurality of fission fuel subassembly is extended along the second dimension.

58. the method as described in provision 51, wherein the first dimension almost axis of elongation with multiple fission fuel subassemblies It is orthogonal.

59. the method as described in provision 51, wherein the first dimension and the second dimension are almost mutually orthogonal.

60. the method as described in provision 51, wherein：

First dimension includes radial dimension；And

Second dimension includes axial dimension.

61. the method as described in provision 51, wherein：

First dimension includes axial dimension；And

Second dimension includes radial dimension.

62. the method as described in provision 51, wherein：

First dimension includes axial dimension；And

Second dimension includes transverse dimensions.

63. the method as described in provision 51, wherein：

First dimension includes transverse dimensions；And

Second dimension includes axial dimension.

64. the method as described in provision 51, wherein：

First position includes outer position；And

The second position includes inner position.

65. the method as described in provision 64, wherein inner position and outer position are based on the central part with reactor core The geometry proximity divided.

66. the method as described in provision 64, wherein inner position and outer position are based on neutron flux so that inner position On neutron flux be more than outer position on neutron flux.

67. the method as described in provision 64, wherein inner position and outer position are based on reactivity so that on inner position K_effectiveMore than the k on outer position_effective。

68. the method as described in provision 51, wherein：

First position includes inner position；And

The second position includes outer position.

69. the method as described in provision 68, wherein inner position and outer position are based on the central part with reactor core The geometry proximity divided.

70. the method as described in provision 68, wherein inner position and outer position are based on neutron flux so that inner position On neutron flux be more than outer position on neutron flux.

71. the method as described in provision 68, wherein inner position and outer position are based on reactivity so that on inner position K_effectiveMore than the k on outer position_effective。

72. the method as described in provision 51, wherein first position and the second position are in reference value along the first dimension On opposite side.

73. the method as described in provision 51, wherein first position and the second position include substantially balanced at least one category Property.

74. the method as described in provision 73, wherein at least one attribute includes several with the central area of reactor core What proximity.

75. the method as described in provision 73, wherein at least one attribute includes neutron flux.

76. the method as described in provision 73, wherein at least one attribute includes reactivity.

77. the method as described in provision 51, wherein determining the selected several along first of multiple fission fuel subassemblies Dimension includes from respective first position to the migration of the respective second position：Determine the selected several of multiple fission fuel subassemblies At least one rotation.

78. the method as described in provision 51, wherein determining the selected several along first of multiple fission fuel subassemblies Dimension includes from respective first position to the migration of the respective second position：Determine the selected several of multiple fission fuel subassemblies It is at least one reverse.

79. the method as described in provision 51, wherein selected group of dimension constraint includes the predetermined maximum along the second dimension Distance.

80. the method as described in provision 51, wherein selected group of dimension constraint is the letter of at least one burnfront criterion Number.

81. the method as described in provision 80, wherein burnfront criterion include neutron flux.

82. the method as described in provision 81, wherein will be several selected by neutron flux and multiple fission fuel subassemblies It is at least one associated.

83. the method as described in provision 80, wherein burnfront criterion include neutron fluence.

84. the method as described in provision 83, wherein will be several selected by neutron fluence and multiple fission fuel subassemblies It is at least one associated.

85. the method as described in provision 80, wherein burnfront criterion include burnup.

86. the method as described in provision 85, wherein by selected by burnup and multiple fission fuel subassemblies it is several extremely Few one associated.

87. the method as described in provision 80, wherein burnfront criterion include the selected of multiple fission fuel subassemblies Several at least one interior burnfront positions.

88. the method as described in provision 51, wherein determining the selected several along first of multiple fission fuel subassemblies Dimension includes from respective first position to the migration of the respective second position：Determine the selected several of multiple fission fuel subassemblies Radial migration along the first dimension from from respective first position to the respective second position.

89. the method as described in provision 51, wherein determining the selected several along first of multiple fission fuel subassemblies Dimension includes from respective first position to the migration of the respective second position：Determine the selected several of multiple fission fuel subassemblies Spiral migration along the first dimension from from respective first position to the respective second position.

90. the method as described in provision 51, wherein determining the selected several along first of multiple fission fuel subassemblies Dimension includes from respective first position to the migration of the respective second position：Determine the selected several of multiple fission fuel subassemblies Axial translation.

91. the method as described in provision 51, wherein determining the desired shape of nuclear fission traveling wave burnfront includes：It determines Nuclear fission traveling wave burnfront it is approximately spherical.

92. the method as described in provision 51, wherein determining the desired shape of nuclear fission traveling wave burnfront includes：It determines The continuous bend surface shape of nuclear fission traveling wave burnfront.

93. the desired shape of the method as described in provision 51, wherein nuclear fission traveling wave burnfront is around the second dimension Degree substantially rotational symmetry.

94. the desired shape of the method as described in provision 51, wherein nuclear fission traveling wave burnfront has around second The substantially n fold rotational symmetry of dimension.

95. the desired shape of the method as described in provision 51, wherein nuclear fission traveling wave burnfront is asymmetrical.

96. the desired shape of the method as described in provision 95, wherein nuclear fission traveling wave burnfront is around the second dimension It spends rotationally asymmetric.

97. a kind of system, comprising：

First circuit is configured to the nuclear fission traveling wave burnfront for being propagated along the first and second dimensions, multiple The institute that nuclear fission traveling wave burnfront is determined along the second dimension is constrained in fission fuel subassembly according to selected group of dimension Desirable shape；And

Second circuit is configured to determine in a manner of shape desired by response several selected by multiple fission fuel subassemblies A migration along the first dimension from respective first position to the respective second position.

98. the system as described in provision 97, wherein the second circuit is further configured to：Determine that nuclear fission traveling wave is burnt The existing shape of front.

99. the system as described in provision 97, wherein the second circuit is further configured to：With shape desired by foundation Mode determines the selected several along the first dimension from respective first position to respective second of multiple fission fuel subassemblies The migration put.

100. the system as described in provision 97, wherein the second circuit is further configured to：With shape desired by maintenance Mode, determine multiple fission fuel subassemblies it is selected it is several along the first dimension from respective first position to respective second The migration of position.

101. the system as described in provision 97, wherein the second circuit is further configured to：With shape desired by response Mode, determine multiple fission fuel subassemblies are migrated along the first dimension from respective first position to the respective second position Selected several time.

102. the system as described in provision 97, plurality of fission fuel subassembly is extended along the second dimension.

103. the system as described in provision 97, wherein the first dimension almost axis of elongation with multiple fission fuel subassemblies It is orthogonal.

104. the system as described in provision 97, wherein the first dimension and the second dimension are almost mutually orthogonal.

105. the system as described in provision 97, wherein：

First dimension includes radial dimension；And

Second dimension includes axial dimension.

106. the system as described in provision 97, wherein：

First dimension includes axial dimension；And

Second dimension includes radial dimension.

107. the system as described in provision 97, wherein：

First dimension includes axial dimension；And

Second dimension includes transverse dimensions.

108. the system as described in provision 97, wherein：

First dimension includes transverse dimensions；And

Second dimension includes axial dimension.

109. the system as described in provision 97, wherein：

First position includes outer position；And

The second position includes inner position.

110. the system as described in provision 109, wherein inner position and outer position are based on the center with reactor core Partial geometry proximity.

111. the system as described in provision 109, wherein inner position and outer position are based on neutron flux so that the inside position The neutron flux put is more than the neutron flux on outer position.

112. the system as described in provision 109, wherein inner position and outer position are based on reactivity so that inner position On k_effectiveMore than the k on outer position_effective。

113. the system as described in provision 97, wherein：

First position includes inner position；And

The second position includes outer position.

114. the system as described in provision 113, wherein inner position and outer position are based on the center with reactor core Partial geometry proximity.

115. the system as described in provision 113, wherein inner position and outer position are based on neutron flux so that the inside position The neutron flux put is more than the neutron flux on outer position.

116. the system as described in provision 113, wherein inner position and outer position are based on reactivity so that inner position On k_effectiveMore than the k on outer position_effective。

117. the system as described in provision 97, wherein first position and the second position are in reference value along the first dimension On opposite side.

118. the system as described in provision 97, wherein first position and the second position include substantially balanced at least one category Property.

119. the system as described in provision 118, wherein at least one attribute includes and the central area of reactor core Geometry proximity.

120. the system as described in provision 118, wherein at least one attribute includes neutron flux.

121. the system as described in provision 118, wherein at least one attribute includes reactivity.

122. the system as described in provision 97, wherein the second circuit is further configured to determine multiple nuclear fission combustions Expect selected several at least one rotation of subassembly.

123. the system as described in provision 97, wherein the second circuit is further configured to determine multiple nuclear fission combustions Expect the selected several at least one reverse of subassembly.

124. the system as described in provision 97, wherein selected group of dimension constraint includes the predetermined maximum along the second dimension Distance.

125. the system as described in provision 97, wherein selected group of dimension constraint is the letter of at least one burnfront criterion Number.

126. the system as described in provision 125, wherein burnfront criterion include neutron flux.

127. the system as described in provision 126, wherein will be several selected by neutron flux and multiple fission fuel subassemblies A is at least one associated.

128. the system as described in provision 125, wherein burnfront criterion include neutron fluence.

129. the system as described in provision 128, wherein will be several selected by neutron fluence and multiple fission fuel subassemblies A is at least one associated.

130. the system as described in provision 125, wherein burnfront criterion include burnup.

131. the system as described in provision 130, wherein will be several selected by burnup and multiple fission fuel subassemblies It is at least one associated.

132. the system as described in provision 125, wherein burnfront criterion include the institute of multiple fission fuel subassemblies Select several at least one interior burnfront positions.

133. the system as described in provision 97, wherein the second circuit is further configured to：Determine multiple nuclear fission combustions Expect selected several radial migrations along the first dimension from respective first position to the respective second position of subassembly.

134. the system as described in provision 97, wherein the second circuit is further configured to：Determine multiple nuclear fission combustions Expect selected several spiral migrations along the first dimension from respective first position to the respective second position of subassembly.

135. the system as described in provision 97, wherein the second circuit is further configured to：Determine multiple nuclear fission combustions Expect selected several axial translation of subassembly.

136. the system as described in provision 97, wherein first circuit is further configured to：Determine that nuclear fission traveling wave is fired Burn the approximately spherical of front.

137. the system as described in provision 97, wherein first circuit is further configured to：Determine that nuclear fission traveling wave is fired Burn the continuous bend surface shape of front.

138. the desired shape of the system as described in provision 97, wherein nuclear fission traveling wave burnfront is around the second dimension Degree substantially rotational symmetry.

139. the desired shape of the system as described in provision 97, wherein nuclear fission traveling wave burnfront has around second The substantially n fold rotational symmetry of dimension.

140. the desired shape of the system as described in provision 97, wherein nuclear fission traveling wave burnfront is asymmetrical.

141. system as described in provision 140, the desired shape of wherein nuclear fission traveling wave burnfront is around second Dimension is rotationally asymmetric.

A kind of 142. computer software program products, comprising：

First computer-readable medium software program code is configured to split for the core propagated along the first and second dimensions Become traveling wave burnfront, determined in multiple fission fuel subassemblies according to selected group of dimension constraint along the second dimension The desired shape of nuclear fission traveling wave burnfront；And

Second computer readable medium software program code, is configured in a manner of shape desired by response, determines multiple Selected several migrations along the first dimension from respective first position to the respective second position of fission fuel subassembly.

143. computer software program product as described in provision 142, wherein the second computer readable medium software Program code is further configured to：Determine the existing shape of nuclear fission traveling wave burnfront.

144. computer software program product as described in provision 142, wherein the second computer readable medium software Program code is further configured to：In a manner of shape desired by foundation, the selected several of multiple fission fuel subassemblies are determined A migration along the first dimension from respective first position to the respective second position.

145. computer software program product as described in provision 142, wherein the second computer readable medium software Program code is further configured to：In a manner of shape desired by maintenance, the selected several of multiple fission fuel subassemblies are determined A migration along the first dimension from respective first position to the respective second position.

146. computer software program product as described in provision 142, wherein the second computer readable medium software Program code is further configured to：In a manner of shape desired by response, determine along the first dimension from respective first position to The respective second position migrates selected several time of multiple fission fuel subassemblies.

147. computer software program product as described in provision 142, plurality of fission fuel subassembly is along Two-dimensions extend.

148. computer software program product as described in provision 142, wherein the first dimension is almost fired with multiple nuclear fissions Expect that the axis of elongation of subassembly is orthogonal.

149. computer software program product as described in provision 142, wherein the first dimension and the second dimension are almost mutual It is orthogonal.

150. computer software program product as described in provision 142, wherein：

First dimension includes radial dimension；And

Second dimension includes axial dimension.

151. computer software program product as described in provision 142, wherein：

First dimension includes axial dimension；And

Second dimension includes radial dimension.

152. computer software program product as described in provision 142, wherein：

First dimension includes axial dimension；And

Second dimension includes transverse dimensions.

153. computer software program product as described in provision 142, wherein：

First dimension includes transverse dimensions；And

Second dimension includes axial dimension.

154. computer software program product as described in provision 142, wherein：

First position includes outer position；And

The second position includes inner position.

155. computer software program product as described in provision 154, wherein inner position and outer position be based on it is anti- Answer the geometry proximity of the central part of heap reactor core.

156. computer software program product as described in provision 154, wherein inner position and outer position are based on neutron Flux so that the neutron flux on inner position is more than the neutron flux on outer position.

157. computer software program product as described in provision 154, wherein inner position and outer position are based on reaction Property so that the k on inner position_effectiveMore than the k on outer position_effective。

158. computer software program product as described in provision 142, wherein：

First position includes inner position；And

The second position includes outer position.

159. computer software program product as described in provision 158, wherein inner position and outer position be based on it is anti- Answer the geometry proximity of the central part of heap reactor core.

160. computer software program product as described in provision 158, wherein inner position and outer position are based on neutron Flux so that the neutron flux on inner position is more than the neutron flux on outer position.

161. computer software program product as described in provision 158, wherein inner position and outer position are based on reaction Property so that the k on inner position_effectiveMore than the k on outer position_effective。

162. computer software program product as described in provision 142, wherein first position and the second position are along first Dimension is on the opposite side of reference value.

163. computer software program product as described in provision 142, wherein first position and the second position are included substantially Balanced at least one attribute.

164. computer software program product as described in provision 163, wherein at least one attribute includes and reactor The geometry proximity of the central area of core.

165. computer software program product as described in provision 163, wherein at least one attribute include neutron flux.

166. computer software program product as described in provision 163, wherein at least one attribute include reactivity.

167. computer software program product as described in provision 142, wherein the second computer readable medium software Program code is further configured to：Determine selected several at least one rotation of multiple fission fuel subassemblies.

168. computer software program product as described in provision 142, wherein the second computer readable medium software Program code is further configured to：Determine the selected several at least one reverse of multiple fission fuel subassemblies.

169. computer software program product as described in provision 142, wherein selected group of dimension constraint is included along the The predetermined maximal distance of two-dimensions.

170. computer software program product as described in provision 142, wherein selected group of dimension constraint is at least one The function of burnfront criterion.

171. computer software program product as described in provision 170, wherein burnfront criterion include neutron flux.

172. computer software program product as described in provision 171, wherein by neutron flux and multiple fission fuels Subassembly it is selected several at least one associated.

173. computer software program product as described in provision 170, wherein burnfront criterion include neutron fluence.

174. computer software program product as described in provision 173, wherein by neutron fluence and multiple fission fuels Subassembly it is selected several at least one associated.

175. computer software program product as described in provision 170, wherein burnfront criterion include burnup.

176. computer software program product as described in provision 175, wherein burnup and multiple fission fuels are grouped Part it is selected several at least one associated.

177. computer software program product as described in provision 170, wherein burnfront criterion include multiple nuclear fissions Selected several at least one interior burnfront position of fuel subassembly.

178. computer software program product as described in provision 142, wherein the second computer readable medium software Program code includes：3rd computer-readable medium software program code is configured to determine multiple fission fuel subassemblies Selected several radial migrations along the first dimension from respective first position to the respective second position.

179. computer software program product as described in provision 142, wherein the second computer readable medium software Program code includes：4th computer-readable medium software program code is configured to determine multiple fission fuel subassemblies Selected several spiral migrations along the first dimension from respective first position to the respective second position.

180. computer software program product as described in provision 142, wherein the second computer readable medium software Program code includes：5th computer-readable medium software program code is configured to determine multiple fission fuel subassemblies Selected several axial translation.

181. computer software program product as described in provision 142, wherein the first computer-readable medium software Program code includes：7th computer-readable medium software program code is configured to determine the big of nuclear fission traveling wave burnfront It causes spherical.

182. computer software program product as described in provision 142, wherein the first computer-readable medium software Program code includes：8th computer-readable medium software program code is configured to determine the company of nuclear fission traveling wave burnfront Continuous curved surface shape.

183. computer software program product as described in provision 142, wherein nuclear fission traveling wave burnfront is desired Shape is around the second dimension substantially rotational symmetry.

184. computer software program product as described in provision 142, wherein nuclear fission traveling wave burnfront is desired Shape has the substantially n fold rotational symmetry around the second dimension.

185. computer software program product as described in provision 142, wherein nuclear fission traveling wave burnfront is desired Shape is asymmetrical.

186. computer software program product as described in provision 185, wherein nuclear fission traveling wave burnfront is desired Shape is rotationally asymmetric around the second dimension.

A kind of 187. systems, comprising：

First circuit is configured to the nuclear fission traveling wave burnfront for being propagated along the first and second dimensions, multiple The institute that nuclear fission traveling wave burnfront is determined along the second dimension is constrained in fission fuel subassembly according to selected group of dimension Desirable shape；

Second circuit is configured to determine in a manner of shape desired by response several selected by multiple fission fuel subassemblies A migration along the first dimension from respective first position to the respective second position；And

Subassembly is configured to respond to the second circuit and migrates the selected several of multiple fission fuel subassemblies.

188. system as described in provision 187, wherein the second circuit is further configured to：Determine that nuclear fission traveling wave is fired Burn the existing shape of front.

189. system as described in provision 187, wherein the second circuit is further configured to：With shape desired by foundation Mode, determine multiple fission fuel subassemblies it is selected it is several along the first dimension from respective first position to respective second The migration of position.

190. system as described in provision 187, wherein the second circuit is further configured to；With shape desired by maintenance Mode, determine multiple fission fuel subassemblies it is selected it is several along the first dimension from respective first position to respective second The migration of position.

191. system as described in provision 187, wherein the second circuit is further configured to：With shape desired by response Mode, determine multiple fission fuel subassemblies are migrated along the first dimension from respective first position to the respective second position Selected several time.

192. system as described in provision 187, plurality of fission fuel subassembly are extended along the second dimension.

193. system as described in provision 187, wherein the almost elongation with multiple fission fuel subassemblies of the first dimension Axis is orthogonal.

194. system as described in provision 187, wherein the first dimension and the second dimension are almost mutually orthogonal.

195. system as described in provision 187, wherein：

First dimension includes radial dimension；And

Second dimension includes axial dimension.

196. system as described in provision 187, wherein：

First dimension includes axial dimension；And

Second dimension includes radial dimension.

197. system as described in provision 187, wherein：

First dimension includes axial dimension；And

Second dimension includes transverse dimensions.

198. system as described in provision 187, wherein：

First dimension includes transverse dimensions；And

Second dimension includes axial dimension.

199. system as described in provision 187, wherein：

First position includes outer position；And

The second position includes inner position.

200. system as described in provision 199, wherein inner position and outer position are based on the center with reactor core Partial geometry proximity.

201. system as described in provision 199, wherein inner position and outer position are based on neutron flux so that the inside position The neutron flux put is more than the neutron flux on outer position.

202. system as described in provision 199, wherein inner position and outer position are based on reactivity so that inner position On k_effectiveMore than the k on outer position_effective。

203. system as described in provision 187, wherein：

First position includes inner position；And

The second position includes outer position.

204. system as described in provision 203, wherein inner position and outer position are based on the center with reactor core Partial geometry proximity.

205. system as described in provision 203, wherein inner position and outer position are based on neutron flux so that the inside position The neutron flux put is more than the neutron flux on outer position.

206. system as described in provision 203, wherein inner position and outer position are based on reactivity so that inner position On k_effectiveMore than the k on outer position_effective。

207. system as described in provision 187, wherein first position and the second position are in reference value along the first dimension Opposite side on.

208. system as described in provision 187, wherein first position and the second position include substantially balanced at least one Attribute.

209. system as described in provision 208, wherein at least one attribute include and the central area of reactor core Geometry proximity.

210. system as described in provision 208, wherein at least one attribute include neutron flux.

211. system as described in provision 208, wherein at least one attribute include reactivity.

212. system as described in provision 187, wherein the second circuit is further configured to：Determine multiple nuclear fission combustions Expect selected several at least one rotation of subassembly.

213. system as described in provision 187, wherein the second circuit is further configured to；Determine multiple nuclear fission combustions Expect the selected several at least one reverse of subassembly.

214. system as described in provision 187, wherein the subassembly includes nuclear fuel management device.

215. system as described in provision 187, wherein the subassembly is further configured to：From respective first position to each From several selected by the multiple fission fuel subassemblies of second position radial migration.

216. system as described in provision 187, wherein the subassembly is further configured to：From respective first position to each It is migrated from second position spiral several selected by multiple fission fuel subassemblies.

217. system as described in provision 187, wherein the subassembly is further configured to：The multiple nuclear fissions of axial translation Fuel subassembly it is selected several.

218. system as described in provision 187, wherein the subassembly is further configured to：Rotate multiple fission fuels Subassembly it is selected several.

219. system as described in provision 187, wherein the subassembly is further configured to：Overturn multiple fission fuels Subassembly it is selected several.

A kind of 220. nuclear fission traveling wave reactors, comprising：

Nuclear fission traveling wave reactor core；

The multiple fission fuel subassemblies being received in the nuclear fission traveling wave reactor core, the multiple nuclear fission Each of fuel subassembly is configured to that nuclear fission traveling wave burnfront is made to propagate along the first and second dimensions wherein；

First circuit is configured to tie up along second according to selected group of dimension constraint in multiple fission fuel subassemblies Degree determines the desired shape of nuclear fission traveling wave burnfront；

Second circuit is configured in a manner of shape desired by response, determines the selected of multiple fission fuel subassemblies Several migrations along the first dimension from respective first position to the respective second position；And

221. reactor as described in provision 220, wherein the second circuit is further configured to：Determine nuclear fission traveling wave The existing shape of burnfront.

222. reactor as described in provision 220, wherein the second circuit is further configured to：With shape desired by foundation The mode of shape, determine multiple fission fuel subassemblies it is selected it is several along the first dimension from respective first position to respective The migration of two positions.

223. reactor as described in provision 220, wherein the second circuit is further configured to：With shape desired by maintenance The mode of shape, determine multiple fission fuel subassemblies it is selected it is several along the first dimension from respective first position to respective The migration of two positions.

224. reactor as described in provision 220, wherein the second circuit is further configured to：With shape desired by response The mode of shape determines to migrate multiple fission fuel subassemblies along the first dimension from respective first position to the respective second position Selected several time.

225. reactor as described in provision 220, plurality of fission fuel subassembly are extended along the second dimension.

226. reactor as described in provision 220, wherein the first dimension is almost stretched with multiple fission fuel subassemblies Long axis is orthogonal.

227. reactor as described in provision 220, wherein the first dimension and the second dimension are almost mutually orthogonal.

228. reactor as described in provision 220, wherein：

First dimension includes radial dimension；And

Second dimension includes axial dimension.

229. reactor as described in provision 220, wherein：

First dimension includes axial dimension；And

Second dimension includes radial dimension.

230. reactor as described in provision 220, wherein：

First dimension includes axial dimension；And

Second dimension includes transverse dimensions.

231. reactor as described in provision 220, wherein：

First dimension includes transverse dimensions；And

Second dimension includes axial dimension.

232. reactor as described in provision 220, wherein：

First position includes outer position；And

The second position includes inner position.

233. reactor as described in provision 232, wherein inner position and outer position based on in reactor core The geometry proximity of center portion point.

234. reactor as described in provision 232, wherein inner position and outer position are based on neutron flux so that the inside Neutron flux on position is more than the neutron flux on outer position.

235. reactor as described in provision 232, wherein inner position and outer position are based on reactivity so that the inside position The k put_effectiveMore than the k on outer position_effective。

236. reactor as described in provision 220, wherein：

First position includes inner position；And

The second position includes outer position.

237. reactor as described in provision 236, wherein inner position and outer position based on in reactor core The geometry proximity of center portion point.

238. reactor as described in provision 236, wherein inner position and outer position are based on neutron flux so that the inside Neutron flux on position is more than the neutron flux on outer position.

239. reactor as described in provision 236, wherein inner position and outer position are based on reactivity so that the inside position The k put_effectiveMore than the k on outer position_effective。

240. reactor as described in provision 220, wherein first position and the second position are in reference along the first dimension On the opposite side of value.

241. reactor as described in provision 220, wherein first position and the second position include substantially balanced at least one Attribute.

242. reactor as described in provision 241, wherein at least one attribute include the central area with reactor core Geometry proximity.

243. reactor as described in provision 241, wherein at least one attribute include neutron flux.

244. reactor as described in provision 241, wherein at least one attribute include reactivity.

245. reactor as described in provision 220, wherein the second circuit is further configured to：Determine multiple nuclear fissions Selected several at least one rotation of fuel subassembly.

246. reactor as described in provision 220, wherein the second circuit is further configured to：Determine multiple nuclear fissions Fuel subassembly it is selected several at least one reverse.

247. reactor as described in provision 220, wherein selected group of dimension constraint was included along the predetermined of the second dimension Maximum range.

248. reactor as described in provision 220, wherein selected group of dimension constraint is at least one burnfront criterion Function.

249. reactor as described in provision 220, wherein burnfront criterion include neutron flux.

250. reactor as described in provision 249, wherein will be selected by neutron flux and multiple fission fuel subassemblies Several is at least one associated.

251. reactor as described in provision 248, wherein burnfront criterion include neutron fluence.

252. reactor as described in provision 251, wherein will be selected by neutron fluence and multiple fission fuel subassemblies Several is at least one associated.

253. reactor as described in provision 248, wherein burnfront criterion include burnup.

254. reactor as described in provision 253, wherein will be several selected by burnup and multiple fission fuel subassemblies It is at least one associated.

255. reactor as described in provision 248, wherein burnfront criterion include multiple fission fuel subassemblies Selected several at least one interior burnfront position.

256. reactor as described in provision 220, wherein the second circuit is further configured to：Determine multiple nuclear fissions Selected several radial migrations along the first dimension from respective first position to the respective second position of fuel subassembly.

257. reactor as described in provision 220, wherein the second circuit is further configured to：Determine multiple nuclear fissions Selected several spiral migrations along the first dimension from respective first position to the respective second position of fuel subassembly.

258. reactor as described in provision 220, wherein the second circuit is further configured to determine multiple nuclear fissions Selected several axial translation of fuel subassembly.

259. reactor as described in provision 220, wherein first circuit is further configured to：Determine nuclear fission traveling wave Burnfront it is approximately spherical.

260. reactor as described in provision 220, wherein first circuit is further configured to：Determine nuclear fission traveling wave The continuous bend surface shape of burnfront.

261. reactor as described in provision 220, the desired shape of wherein nuclear fission traveling wave burnfront are around the Two-dimensions substantially rotational symmetry.

262. reactor as described in provision 220, the wherein desired shape of nuclear fission traveling wave burnfront, which have, to be surrounded The substantially n fold rotational symmetry of second dimension.

263. reactor as described in provision 220, the desired shape of wherein nuclear fission traveling wave burnfront is asymmetric 's.

264. reactor as described in provision 220, the desired shape of wherein nuclear fission traveling wave burnfront are around the Two-dimensions are rotationally asymmetric.

265. reactor as described in provision 220, wherein the subassembly includes nuclear fuel management device.

266. reactor as described in provision 220, wherein the subassembly is further configured to：From respective first position to Each the multiple fission fuel subassemblies of second position radial migration is selected several.

267. reactor as described in provision 220, wherein the subassembly is further configured to：From respective first position to Respective second position spiral migrates the selected several of multiple fission fuel subassemblies.

268. reactor as described in provision 220, wherein the subassembly is further configured to：The multiple cores of axial translation are split Become the selected several of fuel subassembly.

269. reactor as described in provision 220, wherein the subassembly is further configured to：Rotate multiple nuclear fission combustions Expect the selected several of subassembly.

270. reactor as described in provision 220, wherein the subassembly is further configured to；Reverse multiple nuclear fission combustions Expect the selected several of subassembly.

A kind of 271. methods for operating nuclear fission traveling wave reactor, the method include：

By at least one fission fuel assemblies, outwards moved to from the first position in nuclear fission traveling wave reactor core Second position in nuclear fission traveling wave reactor core

272. method as described in provision 271 further includes and at least one nuclear fission combustion is inwardly migrated from the second position Expect component.

273. method as described in provision 271, wherein first position and the second position are based on the center with reactor core Partial geometry proximity.

274. method as described in provision 272, wherein first position and the second position are based on neutron flux so that the inside position The neutron flux put is more than the neutron flux on outer position.

275. method as described in provision 271, wherein first position and the second position are based on reactivity so that inner position On k_effectiveMore than the k on outer position_effective。

A kind of 276. methods for operating nuclear fission traveling wave reactor, the method include：

Determine at least one fission fuel assemblies along a first direction from first in nuclear fission traveling wave reactor core To the migration of the second position in nuclear fission traveling wave reactor core, the second position is different from first position for position；And

Determine migration of at least one fission fuel assemblies along second direction from the second position, second direction is different from First direction.

277. method as described in provision 276, wherein：

First direction is outside；And

Second direction is inside.

278. method as described in provision 277, wherein first position and the second position are based on the center with reactor core Partial geometry proximity.

279. method as described in provision 277, wherein first position and the second position are based on neutron flux so that the inside position The neutron flux put is more than the neutron flux on outer position.

280. method as described in provision 277, wherein first position and the second position are based on reactivity so that inner position On k_effectiveMore than the k on outer position_effective。

281. method as described in provision 276, wherein：

First direction is inside；And

Second direction is outside.

282. method as described in provision 281, the wherein second position and first position are based on the center with reactor core Partial geometry proximity.

283. method as described in provision 281, the wherein second position and first position are based on neutron flux so that the inside position The neutron flux put is more than the neutron flux on outer position.

284. method as described in provision 281, the wherein second position and first position are based on reactivity so that inner position On k_effectiveMore than the k on outer position_effective。

A kind of 285. methods for operating nuclear fission traveling wave reactor, the method include：

By at least one fission fuel assemblies along a first direction from first in nuclear fission traveling wave reactor core The second position moved in nuclear fission traveling wave reactor core is put, the second position is different from first position；And

286. method as described in provision 285, wherein：

First direction is outside；And

Second direction is inside.

287. method as described in provision 286, wherein first position and the second position are based on the center with reactor core Partial geometry proximity.

288. method as described in provision 286, wherein first position and the second position are based on neutron flux so that the inside position The neutron flux put is more than the neutron flux on outer position.

289. method as described in provision 286, wherein first position and the second position are based on reactivity so that inner position On k_effectiveMore than the k on outer position_effective。

290. method as described in provision 286, wherein：

First direction is inside；And

Second direction is outside.

291. method as described in provision 290, the wherein second position and first position are based on the center with reactor core Partial geometry proximity.

292. method as described in provision 290, the wherein second position and first position are based on neutron flux so that the inside position The neutron flux put is more than the neutron flux on outer position.

293. method as described in provision 290, the wherein second position and first position are based on reactivity so that inner position On k_effectiveMore than the k on outer position_effective。

A kind of 294. methods for operating nuclear fission traveling wave reactor, the method include：

At least one fission fuel assemblies are migrated along second direction from the second position, second direction is different from first party To.

295. method as described in provision 294, wherein：

First direction is outside；And

Second direction is inside.

296. method as described in provision 295, wherein first position and the second position are based on the center with reactor core Partial geometry proximity.

297. method as described in provision 295, wherein first position and the second position are based on neutron flux so that the inside position The neutron flux put is more than the neutron flux on outer position.

298. method as described in provision 295, wherein first position and the second position are based on reactivity so that inner position On k_effectiveMore than the k on outer position_effective。

299. method as described in provision 294, wherein：

First direction is inside；And

Second direction is outside.

300. method as described in provision 299, the wherein second position and first position are based on the center with reactor core Partial geometry proximity.

301. method as described in provision 299, the wherein second position and first position are based on neutron flux so that the inside position The neutron flux put is more than the neutron flux on outer position.

302. method as described in provision 299, the wherein second position and first position are based on reactivity so that inner position On k_effectiveMore than the k on outer position_effective。

A kind of 303. methods for operating nuclear fission traveling wave reactor, the method include：

Select predetermined burn up level；And

All to reach the side of the burn up level equal to predetermined burn up level in nearly all multiple fission fuel assemblies Formula determines selected several migration of multiple fission fuel assemblies in fission-type reactor reactor core.

304. method as described in provision 303 further includes：

In a manner that response determines migration, the institute of multiple fission fuel assemblies in fission-type reactor reactor core is migrated It selects several

305. method as described in provision 304 further includes：When burn up level is equal to predetermined burn up level, determine By respective selected several removals of multiple fission fuel assemblies.

306. method as described in provision 305 further includes：It is removed determined by response, removes multiple nuclear fission combustions Expect the selected several of component.

Although having been disclosed for various aspects and embodiment herein, other aspects and embodiment are for the common of this field It is obvious for technical staff.Purpose that various aspects disclosed herein and embodiment are only to be considered illustrative rather than It is intended to limitation, true scope and spirit are pointed out by claims below.

Claims

1. a kind of system that multiple fission fuel subassemblies are migrated in fission-type reactor, comprising：

First circuit is configured to the nuclear fission traveling wave burnfront for being propagated along the first and second dimensions, is split in multiple cores Become in fuel subassembly and constrained according to selected group of dimension, determined along the second dimension desired by nuclear fission traveling wave burnfront Shape；And

Second circuit is configured in a manner of shape desired by response, determines the selected several of multiple fission fuel subassemblies Migration along the first dimension from from respective first position to the respective second position,

Wherein the first dimension and the second dimension are mutually orthogonal.

2. the system as claimed in claim 1, wherein the second circuit is further configured to determine nuclear fission traveling wave burning battle array The existing shape in face.

3. the system as claimed in claim 1, wherein the second circuit is further configured to the side of shape desired by foundation Formula determines the selected several along the first dimension from respective first position to the respective second position of multiple fission fuel subassemblies Migration.

4. the system as claimed in claim 1, wherein the second circuit is further configured to hold desired shape Mode determines the selected several along the first dimension from respective first position to respective second of multiple fission fuel subassemblies The migration put.

5. the system as claimed in claim 1, wherein the second circuit is further configured to the side of shape desired by response Formula determines to migrate selected by multiple fission fuel subassemblies along the first dimension from respective first position to the respective second position Several time.

6. the system as claimed in claim 1, wherein the first dimension is orthogonal with the axis of elongation of multiple nuclear fission subassemblies.

7. the system as claimed in claim 1, wherein：

First dimension includes radial dimension；And

Second dimension includes axial dimension.

8. the system as claimed in claim 1, wherein：

First dimension includes axial dimension；And

Second dimension includes radial dimension.

9. the system as claimed in claim 1, wherein：

First dimension includes axial dimension；And

Second dimension includes transverse dimensions.

10. the system as claimed in claim 1, wherein：

First dimension includes transverse dimensions；And

Second dimension includes axial dimension.

11. the system as claimed in claim 1, wherein：

First position is included in the outer position in reactor core；And

The second position is included in the inner position in reactor core.

12. system as claimed in claim 11, wherein inner position and outer position are based on from at least one selected as follows Attribute：With the geometry proximity of the central part of reactor core；Neutron flux so that the neutron flux on inner position is more than Neutron flux on outer position；And reactivity so that the k on inner position_effectiveMore than on outer position k_effective。

13. the system as claimed in claim 1, wherein：

First position is included in the inner position in reactor core；And

The second position is included in the outer position in reactor core.

14. system as claimed in claim 13, wherein inner position and outer position are based on from at least one selected as follows Attribute：With the geometry proximity of the central part of reactor core；Neutron flux so that the neutron flux on inner position is more than Neutron flux on outer position；And reactivity so that the k on inner position_effectiveMore than on outer position k_effective。

15. the system as claimed in claim 1, wherein first position and the second position are in the phase of reference value along the first dimension On offside.

16. the system as claimed in claim 1, wherein first position and the second position include substantially balanced at least one category Property.

17. system as claimed in claim 16, wherein at least one attribute is included selected from the central area with reactor core One or more of geometry proximity, neutron flux and reactivity attribute.

18. the system as claimed in claim 1, wherein the second circuit is further configured to determine multiple fission fuels point Selected several at least one rotation of component.

19. the system as claimed in claim 1, wherein the second circuit is further configured to determine multiple fission fuels point Component it is selected several at least one reverse.

20. the system as claimed in claim 1, wherein selected group of dimension constraint include along the second dimension it is predetermined it is maximum away from From.

21. the system as claimed in claim 1, wherein selected group of dimension constraint is the letter of at least one burnfront criterion Number.

22. system as claimed in claim 21, wherein burnfront criterion include neutron flux.

23. the system as claimed in claim 22, wherein will be several selected by neutron flux and multiple fission fuel subassemblies It is at least one associated.

24. system as claimed in claim 21, wherein burnfront criterion include neutron fluence.

25. system as claimed in claim 24, wherein will be several selected by neutron fluence and multiple fission fuel subassemblies It is at least one associated.

26. system as claimed in claim 21, wherein burnfront criterion include burnup.

27. system as claimed in claim 26, wherein by selected by burnup and multiple fission fuel subassemblies it is several extremely Few one associated.

28. system as claimed in claim 21, wherein burnfront criterion include the selected of multiple fission fuel subassemblies Several at least one interior burnfront positions.

29. the system as claimed in claim 1, wherein the second circuit is further configured to：Determine multiple nuclear fission combustions Expect selected several radial migrations along the first dimension from respective first position to the respective second position of subassembly.

30. the system as claimed in claim 1, wherein the second circuit is further configured to：Determine multiple nuclear fission combustions Expect selected several spiral migrations along the first dimension from respective first position to the respective second position of subassembly.

31. the system as claimed in claim 1, wherein the second circuit is further configured to：Determine multiple fission fuels Selected several axial translation of subassembly.

32. the system as claimed in claim 1, wherein first circuit is further configured to：It determines to select from following shape A kind of nuclear fission traveling wave burnfront shape：It is approximately spherical；The shape being consistent with selected continuous bend surface；Around second The shape of dimension substantially rotational symmetry；And with the shape around the second dimension substantially n fold rotational symmetry.

33. the desired shape of the system as claimed in claim 1, wherein nuclear fission traveling wave burnfront is asymmetrical.

34. the desired shape of system as claimed in claim 33, wherein nuclear fission traveling wave burnfront is around the second dimension It spends rotationally asymmetric.