CN104021826A - Method for designing axial travelling wave reactor starting area - Google Patents
Method for designing axial travelling wave reactor starting area Download PDFInfo
- Publication number
- CN104021826A CN104021826A CN201410207669.8A CN201410207669A CN104021826A CN 104021826 A CN104021826 A CN 104021826A CN 201410207669 A CN201410207669 A CN 201410207669A CN 104021826 A CN104021826 A CN 104021826A
- Authority
- CN
- China
- Prior art keywords
- heap area
- axial
- length
- heap
- designing
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
Classifications
-
- 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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a method for designing an axial travelling wave reactor starting area. The method comprises the following steps: (a) setting the length of the reactor starting area; (b) axially dividing the reactor starting area; and (c) setting the nuclear density of each axial section of the reactor starting area. According to the reactor starting area designed by the method, after an axial travelling wave reactor stably runs, fuel compositions in each axial section of a main combustion area are quite complicated and comprise fissionable nuclide, fissile nuclide and fission products. Particularly, the fission products affect reactor core reactivity and power distribution greatly due to the difference of kinds and content of the fission products. The four fuels are adopted, so that the combustion condition can be simulated, and the whole power can be regulated by adjusting the content of each composition.
Description
Technical field
The present invention relates to the heap area structure of axial row ripple heap, the specifically method for designing of a kind of axial row Bo Dui heap area.
Background technology
The fundamental starting point of axial row ripple heap is that the consumption of reactor fuel is axially from one end to the other side advancing with certain speed, and in arbitrary moment of full phase in longevity, the reactivity of reactor and axial power distribution shape are substantially constant.Axial row ripple piles up in operational process, and reactor core is axially being divided into San Ge district: spentnuclear fuel district, main combustion zone, fresh fuel district.Main combustion zone is enriched fuel, and neutron fluence rate, far away higher than other Liang Ge districts, is the main energy source of reactor core; Natural uranium, depleted uranium or presurized water reactor spentnuclear fuel can load in fresh fuel district, in main combustion zone and position, boundary, fresh fuel district, the fissilenuclide in fresh fuel district is converted into fissile nuclide by high neutron fluence rate, and along with the propagation of nucleic, move to fresh fuel district with certain speed main combustion zone; In position, boundary, Yu Zhu combustion zone, spentnuclear fuel district, along with the consumption of main combustion zone fissile nuclide and the accumulation of fission product, main combustion zone slowly becomes spentnuclear fuel district herein.Fission reaction will form " ripple of advancing " at heap in-core like this, and ripple is that the image of neutron fluence rate distribution, power distribution, nucleic distribution etc. represents, its concrete combustion process is shown in Fig. 1.
The ultimate principle of axial row ripple heap is breed with the mobile equilibrium of consumption and made in the full phase in longevity of reactor reactivity substantially constant by fissile nuclide, neutron fluence rate distribution shape also constant but with certain speed at Propagation.But because propagation performance, propellant composition and the longevity of initial core difference interim, the end of term in longevity is larger, therefore keep that the reactivity of initial core, neutron fluence rate distribution shape are interim with the longevity, the consistent of the end of term in longevity is difficult to.A kind of method of head it off is to load by rational initial core, and especially the loading of the main combustion zone of initial core fuel is realized, and claims again heap area design.Meanwhile, heap area design rational in infrastructure becomes the gordian technique of axial row ripple heap Core Design.Find by domestic and international new patent searching, do not find that there is at present the literature record that closes heap area method for designing both at home and abroad.
Summary of the invention
The object of the present invention is to provide the method for designing that is applied to a kind of axial row Bo Dui heap area, solve the larger problem of the reactive fluctuation of reactor core in the current full phase in longevity, reach in the full phase in longevity that reactor core reactivity is substantially constant, Important Property Parameters as shape invariances such as neutron fluence rate distribution, power distribution, nucleic distributions but with certain speed the object at Propagation.
Object of the present invention is achieved through the following technical solutions:
A method for designing for axial row Bo Dui heap area, comprises the following steps:
(a) setting of heap area length, when when initial core loads, the length of heap area and axial row ripple are piled stable operation, the length ratio of main combustion zone is 1:0.95～1.05;
(b) heap area axial segmentation arranges, and the heap area axially length of each section is 5～15cm;
(c) the axially setting of each section of nucleon density of heap area, gives axial each section different enrichment fuel is set, and the type of fuel is xU-yPu-zNb-10%Zr, and wherein x, y, z is respectively the mass percent of U, Pu, Nb, and x+y+z+10%=100%.
The method for designing of axial row Bo Dui of the present invention heap area is to have found after studying for a long period of time applicant to propose on the basis of relation between the parameter of heap area and performance:
In described step (a), the length of choosing heap area during with the stable operation of axial row ripple heap the length of main combustion zone identical.Main combustion zone is main energy source, adopt isometric heap area length, can simulate more realistically the combustion case of main combustion zone, to obtain stable combustion state parameter, then give main combustion zone by this stable state transfer, obtain comparatively desirable fired state, the basic the same setting of length is also to keep Important Property Parameters in the constant essential condition of axial shape.
In described step (b), the heap area axially length of each section is 5～15 cm, finds through applicant's repeatedly research, and heap area is better when axially the length of each section is 5～15cm.After the stable operation of axial row ripple heap, axially each section of propellant composition is different in main combustion zone, propagation performance is also different, also while only having fuel axial segmentation to arrange when beginning of life heap area is designed, could simulate the characteristic after the stable operation of row ripple heap, axial segmentation is controlled between 5～15cm, the power difference that can ensure axially each section is little, can be used as again the later stage axially to unload the minimum unit reloading, and is convenient to fuel management.
Described step (c) heap area is axially in the arranging of each section of nucleon density, and the scope of x is 60%～85%, the scope of y is 2%～10%, the scope of z is 0～30%.After the stable operation of axial row ripple heap, main combustion zone axially each section of propellant composition is quite complicated, comprise fissilenuclide, fissile nuclide, fission product etc., especially fission product is because the difference of its kind, content is huge to reactor core reactivity, power distribution influence, adopt this kind of fuel type, can simulate combustion case, can reach the object that regulates overall power by adjusting the content of its each component again.
The present invention compared with prior art, has following advantage and beneficial effect:
1, the method for designing of a kind of axial row Bo Dui of the present invention heap area, when the length of heap area and the stable operation of axial row ripple heap, the length of main combustion zone is basically identical, because main combustion zone is main energy source, the basic the same setting of length is to keep Important Property Parameters in the constant essential condition of axial shape; After the stable operation of axial row ripple heap, axially each section of propellant composition is different in main combustion zone, propagation performance is also different, also while only having fuel axial segmentation to arrange when beginning of life heap area is designed, could simulate the characteristic after the stable operation of row ripple heap, find in the situation that heap area length is definite through long-term research, the hop count axially dividing is more few better, but must be controlled between 5～15cm, so every section of power difference that can ensure axial each section is little, can be used as again the later stage axially unloads the minimum unit reloading, and is convenient to fuel management; After the stable operation of axial row ripple heap, main combustion zone axially each section of propellant composition is quite complicated, comprise fissilenuclide, fissile nuclide, fission product etc., especially fission product is because the difference of its kind, content is huge to reactor core reactivity, power distribution influence, adopt this four kinds of fuel, can simulate combustion case, can reach the object that regulates overall power by adjusting the content of its each component again;
2, the method for designing of a kind of axial row Bo Dui of the present invention heap area, adopt the suitable axial zoning design of heap area length, propellant composition and enrichment, the effectively physical characteristics of Simulation Core after stable, keep heap in-core fissile nuclide propagation and the mobile equilibrium consuming, realize interior reactivity of full phase in longevity substantially constant, the shape invariances such as neutron fluence rate distribution, power distribution, nucleic distribution the target at Propagation with certain speed.
Brief description of the drawings
Fig. 1 is axial row ripple heap combustion mechanism schematic diagram;
Fig. 2 is reactor core general arrangement;
Fig. 3 is heap area step-by-step arrangement figure;
Fig. 4 is the result of Effective multiplication factor;
Fig. 5 is the result that axial power distributes.
Mark and corresponding parts title in accompanying drawing:
1-fresh fuel district, 2-main combustion zone, 3-spentnuclear fuel district, the fresh fuel district in 4-reactor core integral arrangement, 5-heap area, 6-reflection horizon, 7～32 is the mark of each segmentation of heap area.
Embodiment
Below in conjunction with embodiment, the present invention is described in further detail, but embodiments of the present invention are not limited to this.
Embodiment
Schematic diagram as shown in Fig. 1 to 5, the method for designing of a kind of axial row Bo Dui of the present invention heap area, utilizes the method to design an axial row ripple heap reactor core and has obtained remarkable result, and concrete heap area design proposal is as follows:
(a) after calculating and finding that axial row ripple heap Important Property Parameters is as stable in axial power distribution etc., axial span is about 320cm, and the length of heap area is approximately consistent with the span of stable rear Important Property Parameters, is also taken as 320cm;
(b) in order to keep Important Property Parameters if axial power distribution shape etc. is from opening heap just to the end of term in longevity, all constant, when designing, heap area axially carries out segmentation, minimum unit is 5cm, every section of power difference that can ensure axial each section of 5cm is little, can be used as again the later stage axially unloads the minimum unit reloading, and is convenient to fuel management;
(c) table 1 has provided the axially distribution situation of each section of nucleon density of heap area, and wherein axially the content of every section of Zr accounts for 10% of all nucildic masses, Pu other isotopic contents with
239the ratio of Pu is with reference to industrial plutonium, and the kind of nucleon density should be the least possible, and the manufacture that this is beneficial to fuel, reduces costs.
Heap area nucleic distribution situation is as shown in the table:
Fig. 4 provides 60 years K in axial row ripple heap core life
effwith burnup situation of change, K
efffluctuation range be about 0.5%, built-in reactivity less in the phase in longevity had both been beneficial to control, had guaranteed again reactor core safety.Fig. 5 provides axial row ripple heap core life internal power distribution situation, and known axial power distribution shape remains unchanged substantially, and the relative deviation of maximum layer is 8.1%, but with the speed of approximately 5.5 centimetres/year at Propagation.
From Fig. 4, Fig. 5, the heap area of designing according to the inventive method, meeting row ripple, to pile in the full phase in longevity reactivity substantially constant, the shape invariances such as neutron fluence rate distribution, power distribution, nucleic distribution and with certain speed the target at Propagation, and utilized industrial plutonium, be conducive to improve security and the economy of reactor core.
The above, be only preferred embodiment of the present invention, not the present invention done to any pro forma restriction, and any simple modification, the equivalent variations in every foundation technical spirit of the present invention, above embodiment done, within all falling into protection scope of the present invention.
Claims (4)
1. a method for designing for axial row Bo Dui heap area, is characterized in that, comprises the following steps:
(a) setting of heap area length, when when initial core loads, the length of heap area and axial row ripple are piled stable operation, the length ratio of main combustion zone is 1:0.95～1.05;
(b) heap area axial segmentation arranges, and the heap area axially length of each section is 5～15 cm;
(c) the axially setting of each section of nucleon density of heap area, gives axial each section different enrichment fuel is set, and the type of fuel is xU-yPu-zNb-10%Zr, and wherein x, y, z is respectively the mass percent of U, Pu, Nb, and x+y+z+10%=100%.
2. the method for designing of a kind of axial row Bo Dui according to claim 1 heap area, is characterized in that: in described step (a), when the length of heap area is piled stable operation with axial row ripple, the length of main combustion zone is identical.
3. the method for designing of a kind of axial row Bo Dui according to claim 1 heap area, is characterized in that: in described step (b), the heap area axially length of each section is 5～10cm.
4. according to the method for designing of a kind of axial row Bo Dui heap area described in any one in claims 1 to 3, it is characterized in that: described step (c) heap area is axially in the arranging of each section of nucleon density, the scope of x is 60%～85%, the scope of y is 2%～10%, the scope of z is 0～30%.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410207669.8A CN104021826A (en) | 2014-05-16 | 2014-05-16 | Method for designing axial travelling wave reactor starting area |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410207669.8A CN104021826A (en) | 2014-05-16 | 2014-05-16 | Method for designing axial travelling wave reactor starting area |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN104021826A true CN104021826A (en) | 2014-09-03 |
Family
ID=51438540
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201410207669.8A Pending CN104021826A (en) | 2014-05-16 | 2014-05-16 | Method for designing axial travelling wave reactor starting area |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN104021826A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105427898A (en) * | 2015-12-09 | 2016-03-23 | 中国原子能科学研究院 | Multiple-partition mode traveling wave type burning long-life reactor core |
| WO2021259050A1 (en) * | 2020-06-23 | 2021-12-30 | 上海交通大学 | Traveling wave reactor for space exploration |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2002071866A (en) * | 2000-08-30 | 2002-03-12 | Tokyo Inst Of Technol | Reactor core for nuclear reactor and replacing method for nuclear fuel material in the same core |
| JP2003021692A (en) * | 2001-07-09 | 2003-01-24 | Tokyo Inst Of Technol | Core for nuclear reactor, and method for replacing nuclear fuel material in the same core |
| CN102483961A (en) * | 2009-07-31 | 2012-05-30 | 国立大学法人东京工业大学 | Reactor core of nuclear reactor, and nuclear reactor |
| JP2012207962A (en) * | 2011-03-29 | 2012-10-25 | Tokyo Institute Of Technology | Method for manufacturing fuel element of nuclear reactor |
-
2014
- 2014-05-16 CN CN201410207669.8A patent/CN104021826A/en active Pending
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2002071866A (en) * | 2000-08-30 | 2002-03-12 | Tokyo Inst Of Technol | Reactor core for nuclear reactor and replacing method for nuclear fuel material in the same core |
| JP2003021692A (en) * | 2001-07-09 | 2003-01-24 | Tokyo Inst Of Technol | Core for nuclear reactor, and method for replacing nuclear fuel material in the same core |
| CN102483961A (en) * | 2009-07-31 | 2012-05-30 | 国立大学法人东京工业大学 | Reactor core of nuclear reactor, and nuclear reactor |
| JP2012207962A (en) * | 2011-03-29 | 2012-10-25 | Tokyo Institute Of Technology | Method for manufacturing fuel element of nuclear reactor |
Non-Patent Citations (4)
| Title |
|---|
| AKITO NAGATA EL AT.: "A feasible core design of lead bismuth eutectic cooled CANDLE fast reactor", 《ANNALS OF NUCLEAR ENERGY》 * |
| FIBER MONADO，HIROSHI SEKIMOTO EL AT.: "Conceptual design study on very small long-life gas cooled fast reactor using metallic natural Uranium-Zr as fuel cycle input", 《AIP CONFERENCE PROCEEDINGS》 * |
| HIROSHI SEKIMOTO EL AT.: "Startup of ‘‘Candle’’ burnup in fast reactor from enriched uranium core", 《ENERGY CONVERSION AND MANAGEMENT》 * |
| M. KHERADMAND SAADI EL AT.: "Hiroshi Sekimoto el at.", 《ANNALS OF NUCLEAR ENERGY》 * |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105427898A (en) * | 2015-12-09 | 2016-03-23 | 中国原子能科学研究院 | Multiple-partition mode traveling wave type burning long-life reactor core |
| CN105427898B (en) * | 2015-12-09 | 2017-09-12 | 中国原子能科学研究院 | A kind of travelling-wave-type of multi partition pattern burns long core life |
| WO2021259050A1 (en) * | 2020-06-23 | 2021-12-30 | 上海交通大学 | Traveling wave reactor for space exploration |
| US11532404B2 (en) | 2020-06-23 | 2022-12-20 | Shanghai Jiao Tong University | Travelling wave reactor for space exploration |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Yu et al. | Analysis of minor actinides transmutation for a Molten Salt Fast Reactor | |
| Saadi et al. | Startup of “CANDLE” burnup in a Gas-cooled Fast Reactor using Monte Carlo method | |
| Şahin et al. | Utilization of thorium in a gas turbine–modular helium reactor | |
| Ding et al. | Thorium utilization in a small long-life HTR. Part I: Th/U MOX fuel blocks | |
| CN104021826A (en) | Method for designing axial travelling wave reactor starting area | |
| Ariani et al. | Optimization of small long life gas cooled fast reactors with natural Uranium as fuel cycle input | |
| Dalle et al. | Enriched gadolinium burnable poison for PWR fuel–Monte Carlo burnup simulations of reactivity | |
| Monado et al. | Power flattening on modified CANDLE small long life gas-cooled fast reactor | |
| CN104064228B (en) | Row Bo Dui heap area and row Bo Dui heap area manufacture method | |
| Su'ud et al. | Design study of long-life Pb-Bi cooled fast reactor with natural uranium as fuel cycle input using modified CANDLE burn-up scheme | |
| Wilson et al. | Economy of uranium resources in a three-component reactor fleet with mixed thorium/uranium fuel cycles | |
| Su’ud et al. | Desain study of Pb-Bi cooled fast reactors with natural uranium as fuel cycle input using special shuffling strategy in radial direction | |
| Jo et al. | Burnable poison for reactivity management in a very high temperature reactor | |
| Ramdhani et al. | Neutronics analysis of SMART small modular reactor using SRAC 2006 code | |
| CN102194531A (en) | Dual travelling wave partition burning method for fast reactor fuels | |
| Talamo et al. | Performance of the gas turbine-modular helium reactor fuelled with different types of fertile TRISO particles | |
| Xiao et al. | Neutronic study of a molten salt cooled natural thorium–uranium fueled fusion–fission hybrid energy system | |
| Wei et al. | Parametric study of thermal molten salt reactor neutronics criticality behavior | |
| Zheng et al. | Preliminary design study of a board type radial fuel shuffling sodium cooled breed and burn reactor core | |
| Galahom | Improving the neutronic characteristics of a boiling water reactor by using uranium zirconium hydride fuel instead of uranium dioxide fuel | |
| Mirvakili et al. | Computational analysis of neutronic effects of ThO 2 rods loaded in CANDU 6 fuel assemblies | |
| Tavron et al. | Pebble bed reactor fuel cycle optimization using particle swarm algorithm | |
| CN113488205B (en) | Non-uniform tubular MA transmutation rod with function of flattening axial power of reactor core | |
| Zheng et al. | Performance of radial fuel shuffling sodium cooled Breed and Burn reactor core | |
| Kuijper et al. | Neutronics for the GEMINI+ HTGR |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| RJ01 | Rejection of invention patent application after publication | ||
| RJ01 | Rejection of invention patent application after publication |
Application publication date: 20140903 |