WO2017032669A1 - Assembly for an fnr-na-type nuclear reactor, with a housing provided with spacer plates with improved rigidity - Google Patents
Assembly for an fnr-na-type nuclear reactor, with a housing provided with spacer plates with improved rigidity Download PDFInfo
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- WO2017032669A1 WO2017032669A1 PCT/EP2016/069545 EP2016069545W WO2017032669A1 WO 2017032669 A1 WO2017032669 A1 WO 2017032669A1 EP 2016069545 W EP2016069545 W EP 2016069545W WO 2017032669 A1 WO2017032669 A1 WO 2017032669A1
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- Prior art keywords
- assembly
- housing
- sleeve
- reactor
- section
- Prior art date
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- 125000006850 spacer group Chemical group 0.000 title abstract description 7
- 230000003014 reinforcing effect Effects 0.000 claims abstract description 33
- 239000000446 fuel Substances 0.000 claims description 69
- 239000011734 sodium Substances 0.000 claims description 45
- 235000012431 wafers Nutrition 0.000 claims description 44
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 claims description 37
- 229910052708 sodium Inorganic materials 0.000 claims description 37
- 229910000831 Steel Inorganic materials 0.000 claims description 26
- 239000000463 material Substances 0.000 claims description 26
- 239000010959 steel Substances 0.000 claims description 26
- 238000003780 insertion Methods 0.000 claims description 8
- 230000037431 insertion Effects 0.000 claims description 8
- 239000007788 liquid Substances 0.000 claims description 7
- 239000003758 nuclear fuel Substances 0.000 claims description 7
- 229910001338 liquidmetal Inorganic materials 0.000 claims description 6
- 229910000734 martensite Inorganic materials 0.000 claims description 6
- 238000000034 method Methods 0.000 claims description 5
- 230000008961 swelling Effects 0.000 claims description 4
- 229910052797 bismuth Inorganic materials 0.000 claims description 3
- 239000002826 coolant Substances 0.000 claims description 3
- 238000001816 cooling Methods 0.000 claims description 3
- 238000009377 nuclear transmutation Methods 0.000 claims description 3
- 238000009825 accumulation Methods 0.000 claims description 2
- 230000008878 coupling Effects 0.000 claims description 2
- 238000010168 coupling process Methods 0.000 claims description 2
- 238000005859 coupling reaction Methods 0.000 claims description 2
- 230000000712 assembly Effects 0.000 description 44
- 238000000429 assembly Methods 0.000 description 44
- 230000009257 reactivity Effects 0.000 description 6
- 238000006073 displacement reaction Methods 0.000 description 5
- 230000000694 effects Effects 0.000 description 5
- 238000005056 compaction Methods 0.000 description 4
- 238000000605 extraction Methods 0.000 description 4
- 238000004519 manufacturing process Methods 0.000 description 4
- 238000003466 welding Methods 0.000 description 4
- 230000002745 absorbent Effects 0.000 description 3
- 239000002250 absorbent Substances 0.000 description 3
- 238000005452 bending Methods 0.000 description 3
- 238000004364 calculation method Methods 0.000 description 3
- 230000000295 complement effect Effects 0.000 description 3
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- 239000002436 steel type Substances 0.000 description 3
- 241000233805 Phoenix Species 0.000 description 2
- 230000008901 benefit Effects 0.000 description 2
- 230000007547 defect Effects 0.000 description 2
- 238000005086 pumping Methods 0.000 description 2
- 229910001347 Stellite Inorganic materials 0.000 description 1
- 239000011358 absorbing material Substances 0.000 description 1
- 238000000137 annealing Methods 0.000 description 1
- 239000011324 bead Substances 0.000 description 1
- 230000005540 biological transmission Effects 0.000 description 1
- 230000000903 blocking effect Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 229910052804 chromium Inorganic materials 0.000 description 1
- AHICWQREWHDHHF-UHFFFAOYSA-N chromium;cobalt;iron;manganese;methane;molybdenum;nickel;silicon;tungsten Chemical compound C.[Si].[Cr].[Mn].[Fe].[Co].[Ni].[Mo].[W] AHICWQREWHDHHF-UHFFFAOYSA-N 0.000 description 1
- 230000006835 compression Effects 0.000 description 1
- 238000007906 compression Methods 0.000 description 1
- 239000000470 constituent Substances 0.000 description 1
- 238000002788 crimping Methods 0.000 description 1
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- 238000012938 design process Methods 0.000 description 1
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- 230000002349 favourable effect Effects 0.000 description 1
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- 238000005259 measurement Methods 0.000 description 1
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- 230000007935 neutral effect Effects 0.000 description 1
- 238000013021 overheating Methods 0.000 description 1
- 210000004417 patella Anatomy 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 230000002787 reinforcement Effects 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
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Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/324—Coats or envelopes for the bundles
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/322—Means to influence the coolant flow through or around the bundles
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/334—Assembling, maintenance or repair of the bundles
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/02—Details
- G21C5/06—Means for locating or supporting fuel elements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
- G21C1/03—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders cooled by a coolant not essentially pressurised, e.g. pool-type reactors
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- the present invention relates to a fuel assembly for a fast neutron nuclear reactor cooled with liquid metal, especially liquid sodium called RNR-Na or SFR (acronym for "Sodium Fast Reactor") and which is part of the family of so-called reactors. fourth generation.
- liquid metal especially liquid sodium called RNR-Na or SFR (acronym for "Sodium Fast Reactor") and which is part of the family of so-called reactors. fourth generation.
- the aim of the invention is first of all to propose a fuel assembly that can be used in the short term in the fourth generation French technology demonstrator project called ASTRID.
- the fuel assemblies targeted by the invention can be used both in a nuclear reactor of integrated type, that is to say for which the primary circuit of sodium with pumping means is totally contained in a vessel also containing and heat exchangers, only in a loop-type reactor, that is to say for which the intermediate heat exchangers and the primary sodium pumping means are located outside the tank.
- fuel assembly is meant an assembly comprising fuel elements and charged and / or discharged into / from a nuclear reactor.
- fuel assembly type RNR-Na or SFR is meant a fuel assembly adapted to be irradiated in a fast neutron nuclear reactor cooled with liquid sodium called RNR-Na or SFR.
- the invention can be applied to any type of assembly for a nuclear reactor, such as a reflector, a lateral neutron protection (NLP). ), a control bar, an experimental assembly, a complementary safety device ...
- NLP lateral neutron protection
- the fuel assemblies intended for use in fast reactors cooled with liquid sodium (RNR-Na), have a particular mechanical structure in particular to let liquid sodium pass through them.
- FIG. 1 shows a fuel assembly 1 already used in a nuclear reactor RNR-Na known under the name "Phoenix”.
- Such an assembly 1 of elongated shape along a longitudinal axis X firstly comprises a tube or housing 10 with a hexagonal cross-section, the upper portion 11 of which forms the head of gripping the assembly and houses an upper neutron protection device (PNS), and whose central portion 12 envelops fuel needles not shown.
- PPS neutron protection device
- the portions 11, 12 form the same tubular envelope 10 or identical hexagonal section box over its entire height.
- the head 11 of the assembly has a central opening 110 opening therein.
- the assembly 1 finally comprises a lower portion 13 forming the foot of the assembly, in the extension of the housing 10.
- the foot 13 of the assembly has a distal end 15 cone-shaped or rounded to be inserted vertically in the candles of the bed base (support) of a reactor core.
- the foot 13 of the assembly has at its periphery openings 16 opening therein.
- the foot 13 of a male-shaped assembly 1 is inserted into an opening of the reactor base in thus maintaining the assembly 1 in the latter with its longitudinal axis X vertically.
- the primary sodium can circulate inside the housing 10 of the assembly 1 and thus heat-transfer the heat generated by the fuel needles.
- the sodium is thus introduced through the openings 16 of the foot 13 and out through the central opening 110 of the head 11, after having passed through the bundle of combustible needles.
- the central portion 12 of an assembly comprises a plurality of nuclear fuel needles.
- Each needle is in the form of a sealed cylindrical sheath tube inside which is stacked a column 14 of fissile fuel pellets in which occur nuclear reactions that give off heat. All columns 14 define what is usually called the fissile area which is approximately halfway up an assembly 1. It is shown schematically in the form of a black rectangle in FIG.
- All the assemblies of the same reactor are arranged vertically on a bed base to form a core network with hexagonal mesh.
- the assemblies in position on the bed base are spaced from each other at their base (foot), typically a few mm between the facing faces of two adjacent hexagonal section housings.
- these devices are arranged at a height approximately equal to 2/3 of the height of the assembly projecting above the bed base.
- plates consist essentially of bosses, that is to say, extra thickness, projecting outwardly of the assembly.
- Each face of the hexagonal section of the housing is provided with a boss (plate).
- the compaction of the core that is to say a movement of approximation of the assemblies, during an earthquake, or the recompaction of the core following the elastic return of the assemblies after stacking, that is to say a spacing movement of the assemblies generated by a release of energy internal to the core, such as a gas expansion.
- the functional part of these wafers is generally a rectangle of 20 to 50 mm side with a deep drawing depth of the wafers, ie the altitude boss 20 on the face, a few millimeters maximum.
- the inventors have analyzed that the concept of platelets retained for example for fuel assemblies for the earlier reactors, as illustrated in FIGS. 2 to 3C, can not be retained for fuel assemblies for ASTRID, because the existing plates are not enough. rigid with respect to the safety objective sought and presented below, or in other words their stiffness is not high enough.
- the stiffness of a wafer noted K, characterizes the resistance of a wafer to crushing by an external force. It is defined in the elastic range as being equal to the ratio between the force applied to the wafer and the displacement of the face of the wafer with respect to the axis of the hexagonal housing.
- the CFV core negative drain coefficient is the keystone of the safety demonstration for the ASTRID reactor.
- the negative emptying characterized by a natural decrease of reactivity of the heart in case of emptying of the sodium, is reached in particular by minimizing the quantity of steel in the zone, called "plenum", situated just above the combustible needles .
- steel is a reflective material of neutrons.
- a fuel assembly of a CFV core therefore comprises, starting from the top to the bottom of the heart:
- an upper absorbent zone consisting of a neutron-absorbing material
- the horizontal median plane of the intermediate zone of fertile material is located below the horizontal median plane of the assembly formed by the upper zone of fissile material, the intermediate zone of fertile material and the lower zone of fissile material, and the ratio of the height of the intermediate zone of fertile material to the height of the assembly formed by the upper zone of fissile material, the intermediate zone of fertile material and the lower zone of fissile material is in the range of 0, 25 to 0.40.
- the plates are positioned on the hexagonal case just above the upper end of the fuel needles in order to guarantee an optimum spacing between the fissile zones of two adjacent assemblies, and thus to limit the compaction.
- the plates are positioned in the lower part of the plenum.
- the assemblies When they are embedded in the bed base, the assemblies are in contact or near contact at the platelets.
- the compactness of the heart results in a negative or no play at the level of the platelet plane. This compactness is sought in nominal operation, corresponding to average sodium temperatures of about 550 ° C at platelets and 400 ° C at the bed base, to ensure the static mechanical equilibrium of the heart.
- the heart is compact in nominal operation, it is not necessarily cold during tank assembly handling operations, the entire sodium of the tank then being lowered to 200 ° C. Indeed, the level of compactness of the cold core depends on the differential thermal expansion between the steel constituting the bed base and the steel constituting the platelets.
- the bed base is usually made of austenitic steel with a high coefficient of thermal expansion, which is AISI 316 LN stainless steel.
- the inserts can be made either of austenitic steel type AISI 316, whose expansion coefficient is identical to that of the bed base, or martensitic steel type EM10 (9% Cr and 1% Mo) or ferritic steel of which the coefficients of expansion are lower than that of 316 steels.
- the wafers and the bed base are both of austenitic steel: the compactness at the level of the wafers in nominal operation, ie when hot, then implies a positive play on the wafers in handling configuration, ie when cold.
- This positive handling game is favorable for the insertion and extraction of network assemblies by minimizing the friction between assemblies and therefore handling efforts. It also avoids any risk of blocking the assembly in the network;
- the plates are made of ferritic or martensitic steel whereas the base is made of austenitic steel: the compactness of the pads in nominal operation also implies a compactness in the pads in handling with a clearance slightly less than or equal to zero. This negative clearance is unfavorable because it induces significant extraction efforts necessary, at the risk of exceeding the traction capacity of the handling machine, or damage the outer surface of the pads (friction, scratches ).
- the extraction force of the assembly depends on the force applied on the platelets and therefore on their stiffness with imposed displacement, the contact surface between platelets, and the coefficient of friction. In other words, having very rigid pads and / or with a large contact surface is unfavorable vis-à-vis the objective of minimizing the forces during handling assemblies.
- the mounting method selected for an assembly for the ASTRID reactor provides for the insertion of the fuel needle bundle through the top of the hexagonal housing equipped with the welded foot, followed by mounting in the upper part of the assembly consisting of the PNS. and the head to close the assembly.
- the bundle of combustible needles occupies the entire interior space of the hexagonal case.
- the plates being positioned above the needle beam, the feasibility of inserting the latter in the housing therefore depends on the geometry of the wafers.
- the wafers when they have a geometry that does not reduce ⁇ internal interstice of the housing, that is to say the distance separating two facing faces, they do not prevent the insertion of the beam. These platelets of which say non-intrusive.
- the pads can then be mounted or manufactured directly on the original hexagonal case. This type of pads is the simplest and is therefore compatible with assembly assembly.
- the plates have a geometry that reduces the internal gap, such as rigid plates whose thickness is increased towards the inside of the case, they are said to be intrusive and prevent the insertion of the beam from the top of the case. . These pads must then be reported on the housing only once the beam set up.
- spacing plates must be compatible with the thermal hydraulics of the assemblies and the reactor core.
- the pads are oversize provided on the outer faces of the housing, which reduce or locally eliminate the clearance between adjacent assemblies.
- the contact surface, or more precisely the width of the pads should not be too large at the risk of plugging the space between adjacent assemblies and thereby prevent the flow of sodium between the housings of the assemblies.
- the sodium flow between the assemblies is very low and does not participate in the cooling of the assemblies in normal operation.
- the circulation of sodium between the housings of the assemblies which is installed by natural convection in certain accidental situations, such as the loss of primary flow, becomes necessary for the evacuation of the residual power of the assemblies.
- thermohydraulics internal to an assembly is essential for all phases of operation.
- the inventors then sought to identify, among the known solutions of spacing devices between adjacent fuel assemblies in a nuclear reactor vessel, those which could be suitable for guaranteeing a rigid spacing between fuel assemblies for a fourth-generation R R-Na reactor of the ASTRID type. .
- US Pat. No. 4,149,234 discloses a fuel assembly for a nuclear reactor, in particular for an RNR-Na reactor, the hexagonal case of which comprises inserts attached to each face, each plate consisting of two half-platelets arranged next to each other.
- the two half-wafers have the same dimensions, but are made of different materials of which one is chosen to have a low coefficient of friction, for example Stellite, and the other is a steel.
- the arrangement of the half-wafers is such that when two half-wafers of an assembly are in contact with the two half-wafers of the adjacent assembly, each half-wafer is in contact with a half wafer of 'a different material.
- An assembly according to this US4142934 patent is incompatible with the functional specifications of the fourth-generation RNR-Na reactor chips of the ASTRID type, since the platelets each divided into two half-platelets do not make it possible to obtain an increase in their stiffness.
- the patent FR2509896 also discloses a fuel assembly for a nuclear reactor, in particular for a reactor RNR-Na, in which the plates are in the form of stampings in each of the corners of the hexagonal tube of the housing. If the corner pads according to this patent FR 2509896 would allow a priori to increase the stiffness of platelets in the desired proportions, the inventors believe that they can not be retained as a separation solution for RNR-Na reactor of fourth generation of ASTRID type, because of the lack of tolerance that they induce vis-à-vis a defect of angular orientation of the assemblies.
- the patent FR2403626 discloses a fuel assembly for a nuclear reactor, in particular for a reactor RNR-Na, comprising a housing tube with a dodecagonal section with a flat or convex side located in each corner of the tube, in place of a tube with usual hexagonal section for an assembly box.
- This tube geometry with a dodecagonal section makes it possible to limit the expansion of the assembly box under irradiation. This thus guarantees the geometry and the neutron performances of the core since the vibrations are reduced because of the maintenance of the clearances between the fuel needles and the casing, and thus the instabilities of reactivity are limited.
- US Pat. No. 4,543,233 also discloses a fuel assembly for a nuclear reactor RNR-Na, with platelets of circular section housed in the outer face of the hexagonal case and fastened to it by means of a spring washer.
- the patent JP2006145506 discloses a fuel assembly for RNR-Na nuclear reactor, with inserts reported on the outside of the housing of the assembly, similar to those of patent US4543233.
- the plates also of circular section are each housed in a hole made on each side of the tube of the housing and attached to it by screwing or welding.
- the inventors believe that the inserts reported on the outside of the faces of the casing according to the patents US4543233 and JP2006145506 do not lead to a significant increase in stiffness, at least not in the proportions sought for a fourth-generation RNR-Na reactor of the type ASTRID.
- the patent FR2921509 discloses a fuel assembly for a nuclear reactor RNR, in particular of the RNR-Na type, comprising inside the hexagonal case, a six-pointed star-shaped structure, arranged above the bundle of combustible needles. .
- the structure may have longer or shorter branches, and may optionally integrate in addition to lateral bars between branches to stiffen the structure.
- the free end of each of the branches is extended by a spacing plate which passes through an opening in the middle of each face of the housing.
- An assembly according to this patent FR2921509 is not compatible with at least some of the functional specificities of a fourth generation RNR-Na reactor fuel assembly of the ASTRID type.
- the star-shaped structure reported inside the casing constitutes a large mass of steel added in the plenum zone, which necessarily leads to degrade the drainage coefficient to the point of not being able to guarantee the CFV effect of the core.
- the star structure is inherently an obstacle to the flow of sodium in the assembly, with a consequent increase in pressure losses and a disruption of the output flow assembly.
- US4306938 discloses a fuel assembly for RNR-Na nuclear reactor, comprising platelets stamped in the form of a bead or continuous strip over the entire periphery of the hexagonal housing.
- the stamped pads are stiffened by the introduction of a sleeve disposed inside the housing and which is stamped at the same time as the wafers and is housed once deformed in the deformation depression of the wafers.
- the gap behind the pads is then identical to that of the hexagonal case.
- An assembly according to this US4306938 patent can not meet many of the functional specificities of an assembly Fourth generation R R-Na reactor fuel of the ASTRID type.
- the sleeve being housed exactly in the hollow formed by the stamping platelets, its thickness is in fact limited to the drawing depth which is equal to half the distance between two adjacent assemblies, or typically of the order of 1.5 to 3 mm. This thickness is small and insufficient so that the equivalent stiffness of the assembly consisting of the pads and the sleeve, can increase the intrinsic stiffness of the wafers by a factor of 5. Then, the wafers being stamped continuously over the entire outer periphery of the housing they completely clog the space between assemblies. This prevents a circulation of sodium or disrupts the installation of a natural convection between the assemblies.
- the patent application US2014 / 185734 discloses a fuel assembly for RNR-Na nuclear reactor, comprising a double-wall structure housing consisting of an inner tube housed in an outer tube of hexagonal section.
- the inner tube deforms under the effect of internal loads until coming into contact with the outer tube.
- the outer tube cash forces transmitted by the inner tube.
- the good distribution of the deformations / stresses between the two tubes makes it possible to limit the deformations on the outer tube.
- Additional stiffeners may be arranged between the two tubes to limit deformation of the outer tube.
- the problem concerns the transmission of forces, under the effect of the coolant pressure, from the inside of the structure of the internal assembly to the outside.
- the object of the invention is to respond at least in part to this need.
- the subject of the invention is an assembly for a nuclear reactor, in particular for a sodium-cooled fast neutron reactor (RNR-Na), comprising a longitudinal axis housing (X), each main face of the housing comprising, in its central part, a spacing plate with an adjacent assembly, comprising an outwardly protruding portion internally delimiting a hollow without material inside the housing, the assembly further comprising a reinforcing sleeve consisting of a hollow tube adapted to pass the coolant reactor, reported and maintained inside the housing and arranged facing the platelets forming with each of them a cavity.
- RNR-Na sodium-cooled fast neutron reactor
- the housing is of hexagonal section.
- each wafer is a stamped wafer, the sleeve being arranged opposite stamping recesses of the wafers.
- each wafer has an outer surface of contact with the adjacent assembly, which has a rectangular shape.
- the reinforcing sleeve further comprises an inclined straight edge forming a convergent connecting the inner periphery of the underside of the sleeve to the outer periphery of the underside of the sleeve and an inclined straight edge forming a divergent connecting the inner periphery of the sleeve.
- the pads reinforced by means of a sleeve according to the invention constitute intrusive plates insofar as the reported sleeve is an obstacle to the flow of sodium in the assembly.
- the reinforcing sleeve has a height less than that of the plates, the heights being measured along the longitudinal axis (X).
- the reinforcing sleeve may, on the other hand, have a height greater than that of the stamped inserts, the heights being measured along the longitudinal axis (X).
- the sleeve comprises means for allowing the filling and emptying of liquid and the non-accumulation of gas inside each cavity formed between the sleeve and a wafer.
- These means may advantageously consist of at least two holes passing through the sleeve, which each open into each cavity formed between the sleeve and a plate, these holes being located respectively at the lower part and the upper part of the cavity.
- the reinforcing sleeve comprises a hollow cylinder of height greater than or equal to that of the wafers and of outer diameter substantially equal to the largest dimension of the internal cross section of the housing.
- the reinforcing sleeve comprises a part whose outer periphery comprises hexagonal portions matching the hexagonal inner section of the housing.
- the inner periphery may be circular in cross section.
- the reinforcing sleeve comprises a part whose outer periphery is of hexagonal cross-section matching the hexagonal inner section of the housing.
- the inner periphery may also be of hexagonal cross-section, the height of the inner periphery of the part being less than that of its outer periphery.
- the reinforcing sleeve is made of a material whose coefficient of thermal expansion and irradiation swelling is greater than that of the housing material comprising the wafers of the assembly.
- the reinforcing sleeve is preferably made of austenitic steel and the housing is preferably made of ferritic or martensitic steel.
- the reinforcing sleeve is attached to one or more structures of the assembly by attachment means disposed at the periphery of the internal section of the housing. housing.
- the assembly which has just been described advantageously constitutes a fuel assembly, the housing being intended to be inserted vertically into the support of the reactor core, the housing comprising an upper part forming the head of the assembly housing a device for superior neutron protection (SNP) consisting of neutron absorbents and a central portion housing nuclear fuel needles, the spacing plates being disposed in a plane above the fuel needles.
- SNP superior neutron protection
- the coupling means of the sleeve are rods connected to the lower structures of the PNS.
- the fuel assembly as defined makes it possible to meet the specifications of the spacers of a fuel assembly for RNR-Na reactor of fourth generation of ASTRID type.
- the assembly described may also constitute any other type of non-combustible assembly that can be inserted in a reactor core cooled with sodium RNR-Na, such as for example a reflector assembly, a Neutron Side Protection (NLP) assembly, a control bar, an experimental assembly, a complementary safety device, a breeder assembly or a transmutation assembly.
- NLP Neutron Side Protection
- the invention also relates to a method for producing an assembly described above, comprising the following steps:
- the invention also relates to the use of a fuel assembly described above in a fast neutron nuclear reactor RR, such as a reactor cooled with gas or liquid metal, the liquid metal being chosen from sodium, lead or lead-bismuth.
- FIG. 1 is an external perspective view of a fuel assembly according to the state of the art, already used in a sodium-cooled nuclear reactor R R-Na;
- FIG. 2 is a perspective view of a fuel assembly according to the state of the art, which has already been used in the "Phoenix" nuclear reactor, the figure showing the devices in the form of spacing plates with an assembly adjacent fuel in the reactor core;
- FIG. 2A is a longitudinal sectional view of a fuel assembly envisaged for ASTRID at the beginning of the project, showing more precisely the positioning of the plates relative to the other elements of the assembly;
- FIGS. 3A and 3B are respectively perspective and cross-sectional views of a portion of a hexagonal fuel assembly cross-section housing according to FIGS. 2 and 2A showing the stampings forming the plates;
- FIG. 3C is a front detail view of a wafer according to FIGS. 3A and 3B;
- FIG. 4 is identical to Figure 3B and shows the deformation of a face of the housing when it is subjected to a force applied to a wafer while the three opposite faces of the housing are maintained;
- FIG. 5 is a cross-sectional view of a portion of a hexagonal cross-section housing fuel assembly showing a platelet spacing device according to FIG. 2A and an attached sleeve according to the invention, as envisaged. for the ASTRID nuclear reactor;
- FIG. 6 is a perspective view of a portion of a box with hexagonal section with stamped plates showing a first variant of the sleeve according to the invention
- FIG. 7 is a perspective view of a portion of a box with hexagonal section with stamped plates showing a second variant of the sleeve according to the invention.
- FIG. 8 is a perspective view of a portion of a box with hexagonal section with stamped plates showing a third variant of the sleeve according to the invention.
- FIG. 9 is a perspective view of a portion of a hexagonal section housing with stamped plates showing the third variant of the sleeve according to the invention with its fixing means inside the assembly housing;
- FIG. 10 is a detailed sectional view of an advantageous variant of a reinforcing sleeve according to the invention for improving the thermohydraulic within the fuel assembly which is provided;
- FIGS. 11A and 11B are schematic sectional views of another advantageous variant of a reinforcing sleeve according to the invention for improving the thermohydraulic within the fuel assembly which is provided.
- FIG. 12 is a schematic sectional view of a reinforcing sleeve according to the invention with a dodecagonal section fixed in a hexagonal section of the assembly housing.
- the inventors analyzed the deformation mode platelets.
- the low stiffness of a wafer 2 made by stamping is characterized, by crushing force given on this wafer, by a significant displacement thereof.
- the inventors have been able to demonstrate that this displacement or significant erasure of the wafer subjected to a force is caused firstly by the bending deformation of the face of the hexagonal case which integrates the wafer in question. This phenomenon has been reproduced by finite element calculation and is shown in FIG.
- the inventors then thought to reinforce the inside of the stampings 2 by a reinforcing sleeve 3 added and held inside the hexagonal-section box 10 and positioned opposite the plates 20, more precisely at the hollow 21 of the stampings of the platelets 2.
- FIG. 5 A fuel assembly 1 incorporating such a sleeve 3 according to the invention, as it is intended to be used in a nuclear R R-Na reactor of the ASTRID type, is shown in FIG. 5.
- the assembly 1 according to the invention is of elongated shape along a longitudinal axis X and comprises a housing 10 having a hexagonal cross-section, the end of the upper portion 11 of which forms the head of the assembly, and which surrounds a neutron protection device called PNS comprising neutron absorbents 18.
- the central portion 12 of the assembly 1 envelops fuel needles 14 forming the fissile area of the assembly.
- the assembly 1 finally comprises a lower portion not shown forming the foot of the assembly, in the extension of the housing 10, as in the assembly according to the state of the art.
- the foot of the assembly has a distal end cone-shaped or rounded to be inserted vertically into the bed base of a reactor core.
- the foot of the assembly also has at its periphery openings opening therein for the entry of sodium into the assembly.
- the reinforcing sleeve 3 As shown in FIG. 5, the reinforcing sleeve 3 according to the invention is housed and held inside the casing 10 above the fuel needles 14 and positioned facing the platelet embossing recesses 2.
- Each stamped wafer 2 always has an outer surface 20 of contact with the adjacent assembly, which has a rectangular shape and which is not impacted by the sleeve 3, each wafer 2 still having a pressed recess 21 without material to the inside the case.
- platelets in other forms, such as circular, or any other form feasible and satisfying the constraints of spacing and rigidity sought.
- the reinforcing sleeve 3 makes it possible to limit the deformation by bending of each of the six faces of the casing 10 and thus to increase the stiffness of the stamped plates 2.
- the overall equivalent stiffness is then the sum of the stiffness of the stamped plates 2 and the stiffness of the sleeve 3.
- the reinforcing sleeve 3 being an insert inside the housing 3, it can be given a multitude of geometries (shape of the section, thickness, height) according to the stiffness and the constraints of manufacture / assembly inherent to the assembly.
- FIGS. 6 to 8 Three different sleeve geometry variants are shown in FIGS. 6 to 8 which can therefore be:
- outer periphery 30 can be connected to the inner periphery 31 by a central rib 32 ( Figure 8), the radial section of the sleeve is then in the shape of a "T".
- the sleeve 3 is made of a material whose coefficient of thermal expansion and swelling under irradiation is greater than that of the housing material comprising the wafers of the assembly.
- the sleeve 3 is austenitic steel type AISI 316, because it is the material that has the best compromise vis-à-vis the functions to be completed in the context of a fuel assembly 1 for nuclear reactor RNR-Na of type ASTRID, provided with a case of martensitic steel of type EM10.
- FIG. 9 shows an advantageous variant of attachment of the sleeve 3 "of FIG. 8.
- the sleeve 3" is hooked (suspended) to the fixed lower structures of the PNS (not shown) by means of rods 4 are each arranged in an angle of the internal hexagonal section of the housing 10.
- the attachment rods 4 shown are circular section but any other section may be suitable. With such hooking rods 4, the mounting method of the fuel assembly is compatible with the reference assembly range already advanced for the ASTRID reactor, only the connection of the sleeve 3 with the PNS being added as a preliminary step .
- the advantage of the mounting method according to the invention of the sleeve 3 in the housing 10 is that it does not require additional mechanical connection between the sleeve 3 with the housing 10, of the welding, screwing, crimping ...
- the sleeve 3 is inserted with play inside the housing 10. It must then be ensured that the sleeve clearance 3 is correctly calibrated with respect to the inner wall of the housing 10.
- the clearance must be strictly positive and of sufficient value when mounting the sleeve 3 in the housing 10, that is to say in a workshop atmosphere ambient temperature of about 20 ° C;
- the clearance must be zero or slightly negative (clamping) nominal reactor operation, that is to say at a temperature of 550 ° C average platelets 2. This condition ensures good contact between the sleeve 3 and the housing 10 in order to effectively have the increase in stiffness of platelets sought in the context of the invention.
- the sleeve 3 is made of austenitic steel, which has a coefficient of thermal expansion and swelling under higher flux than the casing 10 of ferritic steel or martensitic. As a result, the backlash in operation at 550 ° C between sleeve 3 and casing 10 is facilitated;
- the sleeve 3 For mounting the sleeve 3 in the housing 10, the latter is preheated to a temperature of about 100 to 200 ° C while the sleeve 3 is maintained at about 20 ° C.
- the difference in expansion between the two constituent steels thus makes it possible to increase the mounting clearance;
- the external dimensions of the sleeve 3, which define the contact surface with the housing 10 are machined at the last moment before mounting and adapted according to the actual measurement of the inner gap of the TH. This eliminates manufacturing tolerances of the housing 10 which can be relatively large.
- the sleeve 3 according to the invention can be chosen with a height independent of the height of the wafers 2, unlike the sleeve solution according to US4306938 which has de facto the same height as that of the wafers .
- a sleeve 3 as shown in FIG. 10, of useful height H1 equal to 50 mm for stamped plates 2 having a height stamping h of 80 mm is quite satisfactory.
- the thickness E of the sleeve 3 necessary to increase the stiffness by a factor of 5 is 8.6 mm.
- an advantageous variant illustrated in FIG. 10 consists in producing the sleeve 3 with an inclined straight edge 33 forming a convergent connecting the inner periphery 31 of the underside of the sleeve to the outer periphery 30 of the underside of the sleeve and an inclined straight edge 34 forming a diverging connecting the inner periphery 31 of the top of the sleeve to the outer periphery 30 of the top of the sleeve 3.
- This variant is all the more effective as the thickness of the sleeve is important.
- the volume between the stamped plate 2 and the sleeve 3 is delimited by the stamping cavity 21 and forms a closed cavity . It is then necessary to provide, in the lower part of the convergent 33, at least one opening hole for filling and emptying the liquid sodium of this cavity. At least one other hole opening in the upper part of the diverging part may also be necessary in order to avoid trapping gas when filling the sodium cavity.
- openings opening 35, 36 respectively larger or smaller in the thickness of the sleeve and allow to pass the sodium.
- the inventors believe that this solution is less optimized than a convergent / divergent solution, and that it can not be applied to high throughput assemblies or those requiring high platelet stiffness.
- the invention was able to meet the need for fuel assemblies for the ASTRID reactor, to namely an increase in platelet stiffness by a factor of 5 compared to the state of the art while maintaining a negative drain coefficient, and being compatible with the handling, manufacture and thermohydraulics of the reactor.
- a fuel assembly 1 according to the invention which has just been described thus makes it possible to meet all the functional specifications of spacing of a fuel assembly of a fourth-generation RNR nuclear reactor such as ASTRID.
- the invention has been described in the particular context of a fuel assembly for a fourth generation RNR nuclear reactor such as ASTRID, that is to say CFV core, which involves many constraints to be checked simultaneously.
- a non-CFV core architecture allows a quasi free choice of the dimensions of the sleeve (unlimited steel quantity);
- pads it may be platelets stamped in the housing, but also any other type of non-stamped and non-intrusive pads, such as inserts reported on the outside of the housing;
- RNR fast neutron nuclear fuel
- the reinforcing sleeve described 3 can also be added to reinforce any other type of assembly present in a core of RNR, such as a reflector assembly, a Neutral Neutron Protection (NLP) assembly. , a bar command, an experimental assembly, a complementary safety device, a breeder assembly, a transmutation assembly, etc.
- NLP Neutral Neutron Protection
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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Manufacturing & Machinery (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
Claims
Priority Applications (4)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
RU2018105774A RU2678573C1 (en) | 2015-08-21 | 2016-08-17 | Assembly for nuclear reactor on fast neutrons with sodium cooling, with housing with spacing gaskets of improved rigidity |
JP2018509767A JP2018528421A (en) | 2015-08-21 | 2016-08-17 | Assembly for an FNR-NA reactor having a housing with a spacer plate having improved stiffness |
CN201680059227.0A CN108140435B (en) | 2015-08-21 | 2016-08-17 | Assembly of a nuclear reactor of the sodium-cooled fast reactor type, the shell of which is equipped with spacer plates of increased rigidity |
KR1020187007952A KR20180041223A (en) | 2015-08-21 | 2016-08-17 | An assembly for an FNR-NA-type reactor having a housing provided with a spacer plate with improved rigidity |
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR1557860A FR3040234B1 (en) | 2015-08-21 | 2015-08-21 | ASSEMBLY FOR RNR-NA TYPE NUCLEAR REACTOR, HAVING A BOX PROVIDED WITH ENHANCED STIFFNESS SPACER PLATES |
FR1557860 | 2015-08-21 |
Publications (1)
Publication Number | Publication Date |
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WO2017032669A1 true WO2017032669A1 (en) | 2017-03-02 |
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Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
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PCT/EP2016/069545 WO2017032669A1 (en) | 2015-08-21 | 2016-08-17 | Assembly for an fnr-na-type nuclear reactor, with a housing provided with spacer plates with improved rigidity |
Country Status (6)
Country | Link |
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JP (1) | JP2018528421A (en) |
KR (1) | KR20180041223A (en) |
CN (1) | CN108140435B (en) |
FR (1) | FR3040234B1 (en) |
RU (1) | RU2678573C1 (en) |
WO (1) | WO2017032669A1 (en) |
Families Citing this family (2)
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RU2745348C1 (en) * | 2019-12-31 | 2021-03-24 | Акционерное общество "АКМЭ-инжиниринг" (сокращенно АО "АКМЭ-инжиниринг") | Integral nuclear reactor (options) |
KR102510440B1 (en) * | 2022-12-16 | 2023-03-15 | 터보파워텍(주) | Method for nuclear fuel rod spacer grid by 3D printing laser cladding |
Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
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JPS4729199U (en) * | 1971-04-30 | 1972-12-02 | ||
JPH01172797A (en) * | 1987-12-26 | 1989-07-07 | Hitachi Ltd | Fast breeder reactor |
FR2921509A1 (en) * | 2007-09-21 | 2009-03-27 | Areva Np Sas | COMBUSTIBLE ASSEMBLY FOR FAST NEUTRON NUCLEAR REACTOR |
Family Cites Families (13)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS51140089A (en) * | 1975-05-28 | 1976-12-02 | Toshiba Corp | Fuel aggregate |
CA1083270A (en) * | 1976-04-26 | 1980-08-05 | Kiyozumi Hayashi | Fuel assembly spacer |
DE2656441C2 (en) * | 1976-12-14 | 1986-10-16 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | Spacer plaster for the mutual support of hexagonal fuel assembly boxes of a fast, sodium-cooled breeder reactor |
US4229259A (en) * | 1977-09-08 | 1980-10-21 | Westinghouse Electric Corp. | Grid sleeve bulge tool |
JPS6027392B2 (en) * | 1978-02-03 | 1985-06-28 | 株式会社日立製作所 | core components |
SE425272B (en) * | 1981-02-03 | 1982-09-13 | Asea Atom Ab | Nuclear Reactor Fuel Cartridge |
JPS63195590A (en) * | 1987-02-09 | 1988-08-12 | 株式会社東芝 | Nuclear reactor |
RU2256243C2 (en) * | 2003-06-02 | 2005-07-10 | Открытое акционерное общество "Новосибирский завод химконцентратов" | Nuclear reactor fuel assembly |
JP4559965B2 (en) * | 2005-12-27 | 2010-10-13 | 株式会社東芝 | Nuclear fuel assembly |
FR2951312B1 (en) * | 2009-10-08 | 2011-12-09 | Commissariat Energie Atomique | NUCLEAR FUEL ASSEMBLY BODY AND NUCLEAR FUEL ASSEMBLY COMPRISING SUCH A BODY |
FR2951578B1 (en) * | 2009-10-16 | 2012-06-08 | Commissariat Energie Atomique | ASSEMBLY OF NUCLEAR FUEL AND NUCLEAR REACTOR COMPRISING AT LEAST ONE SUCH ASSEMBLY |
US9576685B2 (en) * | 2012-04-26 | 2017-02-21 | Ge-Hitachi Nuclear Energy Americas Llc | Fuel bundle for a liquid metal cooled nuclear reactor |
US9721678B2 (en) * | 2013-05-17 | 2017-08-01 | Terrapower, Llc | Nuclear fuel assembly design |
-
2015
- 2015-08-21 FR FR1557860A patent/FR3040234B1/en active Active
-
2016
- 2016-08-17 JP JP2018509767A patent/JP2018528421A/en active Pending
- 2016-08-17 RU RU2018105774A patent/RU2678573C1/en not_active IP Right Cessation
- 2016-08-17 WO PCT/EP2016/069545 patent/WO2017032669A1/en active Application Filing
- 2016-08-17 KR KR1020187007952A patent/KR20180041223A/en active IP Right Grant
- 2016-08-17 CN CN201680059227.0A patent/CN108140435B/en active Active
Patent Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS4729199U (en) * | 1971-04-30 | 1972-12-02 | ||
JPH01172797A (en) * | 1987-12-26 | 1989-07-07 | Hitachi Ltd | Fast breeder reactor |
FR2921509A1 (en) * | 2007-09-21 | 2009-03-27 | Areva Np Sas | COMBUSTIBLE ASSEMBLY FOR FAST NEUTRON NUCLEAR REACTOR |
Also Published As
Publication number | Publication date |
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CN108140435B (en) | 2021-10-29 |
RU2678573C1 (en) | 2019-01-30 |
JP2018528421A (en) | 2018-09-27 |
FR3040234A1 (en) | 2017-02-24 |
FR3040234B1 (en) | 2019-10-25 |
KR20180041223A (en) | 2018-04-23 |
CN108140435A (en) | 2018-06-08 |
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