CN103151084B - A kind of pressurized water reactor core and New Parent thereof reload stowage - Google Patents
A kind of pressurized water reactor core and New Parent thereof reload stowage Download PDFInfo
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- CN103151084B CN103151084B CN201310055944.4A CN201310055944A CN103151084B CN 103151084 B CN103151084 B CN 103151084B CN 201310055944 A CN201310055944 A CN 201310055944A CN 103151084 B CN103151084 B CN 103151084B
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- reactor core
- new parent
- pressurized water
- water reactor
- burnup
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- 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
Abstract
The invention discloses a kind of pressurized water reactor core and New Parent thereof to reload stowage, this New Parent stowage of reloading comprises: load the assembly of burnup that a collection of New Parent draws off same quantity simultaneously, for the New Parent with a collection of loading, wherein a part of New Parent will draw off reactor core after the N number of circulation of burnup in reactor core, remainder will draw off reactor core after burnup N+1 circulation in reactor core, wherein, N is natural number, and the uranium enrichment of described a part of New Parent when entering to pile first is lower than the uranium enrichment of described remainder New Parent when entering to pile first.Implement technical scheme of the present invention, after New Parent uses two kinds of enrichment assemblies, comparatively low enrichment can be used to the assembly of the less circulation of burnup, reduce fuel cost; And, can be reduced it and remain uranium enrichment when drawing off reactor core, and improve fuel service efficiency.
Description
Technical field
The present invention relates to pressurized-water reactor nuclear power plant fuel management field, especially relate to a kind of pressurized water reactor core and New Parent reload core stowage thereof.
Background technology
Current domestic pressurized-water reactor nuclear power plant long period reloads, and within 18 months, reloading, uses a kind of novel fuel assembly of uranium enrichment to carry out core loading conceptual design.Current domestic pressurized-water reactor nuclear power plant year reloads, and is also to use a kind of novel fuel assembly of uranium enrichment to carry out core loading conceptual design.
Illustrate for the kilowatt pressurized water reactor nuclear power station balanced recycle loading pattern that reloads for 18 months.Kilowatt pressurized water reactor nuclear power station 157 groups of assembly reactor cores are arranged as 15 row * 15 and arrange, and its reactor core adopts square cross section vertical prismatic shape assembly.As shown in Figure 1, be that 8 row * 8 arrange, wherein each grid represents one group of assembly to its reactor core 1/4th cross sectional arrangement.As shown in Figure 1, current domestic pressurized-water reactor nuclear power plant long period reloads, and within 18 months, reloading, only uses a kind of novel fuel assembly of uranium enrichment to carry out core loading conceptual design.Whole reactor core 157 groups of assemblies, wherein novel fuel assembly 72 groups, employs the assembly of uranium enrichment 4.45%; In reactor core, the assembly of burnup second circulation has 68 groups, carries out uranium enrichment when first circulation burnup enters to pile be similarly 4.45% at it; In reactor core, the assembly of burnup the 3rd circulation has 16 groups, carries out uranium enrichment when first circulation burnup enters to pile be similarly 4.45% at it; Separately employ one group of assembly as center element.Consider, with the service condition of a collection of 72 groups of assemblies at heap in-core, can find out, draw off reactor core after only having 16 groups of assemblies burnup three to be circulated, all the other 56 groups of assemblies draw off reactor core after burnup two circulation.Owing to only employing same uranium enrichment 4.45% with a collection of 72 groups of assemblies, like this, when drawing off reactor core, draw off reactor core assembly after three circulations of 16 groups of burnups, burnup is higher, and residue uranium enrichment is less; And assembly burnup is less after two circulations of 56 groups of burnups, residue uranium enrichment is still higher, causes waste.
Summary of the invention
The technical problem to be solved in the present invention is, for the above-mentioned defect of prior art, provides a kind of pressurized water reactor core and New Parent thereof to reload stowage, reduces fuel cost, and can improve fuel service efficiency.
The technical solution adopted for the present invention to solve the technical problems is: the New Parent constructing a kind of pressurized water reactor core reloads stowage, load the assembly of burnup that a collection of New Parent draws off same quantity simultaneously, for the New Parent with a collection of loading, wherein a part of New Parent will draw off reactor core after the N number of circulation of burnup in reactor core, remainder New Parent will draw off reactor core after burnup N+1 circulation in reactor core, wherein, N is natural number, and, the uranium enrichment of described a part of New Parent when entering to pile first is lower than the uranium enrichment of described remainder New Parent when entering to pile first.
Reload in stowage at the New Parent of pressurized water reactor core of the present invention, described N is 2.
Reload in stowage at the New Parent of pressurized water reactor core of the present invention, the uranium enrichment of described a part of New Parent when entering to pile first is 4.2%, and the uranium enrichment of described remainder New Parent when entering to pile first is 4.45%.
Reload in stowage at the New Parent of pressurized water reactor core of the present invention, in described New Parent, add burnable poison.
Reload in stowage at the New Parent of pressurized water reactor core of the present invention, described a part of New Parent be arranged on pressurized water reactor core with upper/lower positions: B08, B09, C09, D08, D10, D12, E09, E11, F10, F12, G09, G11, G13, G14, H12, H14; Described remainder New Parent be arranged on pressurized water reactor core with upper/lower positions: B10, C11, E13, F14, and the arrangement of whole reactor core is 1/4 Rotational Symmetry by above-mentioned position.
The present invention also constructs a kind of pressurized water reactor core, described pressurized water reactor core is equipped with a collection of New Parent, wherein a part of New Parent will draw off reactor core after the N number of circulation of burnup in reactor core, remainder New Parent will draw off reactor core after burnup N+1 circulation in reactor core, wherein, N is natural number, and the uranium enrichment of described a part of New Parent when entering to pile first is lower than the uranium enrichment of described remainder New Parent when entering to pile first.
In pressurized water reactor core of the present invention, described N is 2.
In pressurized water reactor core of the present invention, the uranium enrichment of described a part of New Parent when entering to pile first is 4.2%, and the uranium enrichment of described remainder New Parent when entering to pile first is 4.45%.
In pressurized water reactor core of the present invention, described New Parent includes burnable poison.
In pressurized water reactor core of the present invention, described a part of New Parent be arranged on pressurized water reactor core with upper/lower positions: B08, B09, C09, D08, D10, D12, E09, E11, F10, F12, G09, G11, G13, G14, H12, H14; Described remainder New Parent be arranged on pressurized water reactor core with upper/lower positions: B10, C11, E13, F14, and the arrangement of whole reactor core is 1/4 Rotational Symmetry by above-mentioned position.
Implement technical scheme of the present invention, after New Parent uses two kinds of enrichment assemblies, comparatively low enrichment can be used to the assembly of the less circulation of burnup, reduce fuel cost; And, can be reduced it and remain uranium enrichment when drawing off reactor core, and improve fuel service efficiency.
Accompanying drawing explanation
Below in conjunction with drawings and Examples, the invention will be further described, in accompanying drawing:
Fig. 1 is the cross-sectional view of whole reactor core 1/4th in prior art;
Fig. 2 is the cross-sectional view of whole reactor cores 1/4th of the embodiment of the present invention one.
Embodiment
Pressurized water reactor core generally adopts batch mode of reloading, and namely loads the assembly of burnup that a collection of New Parent also draws off same quantity simultaneously, to keep reactor fuel component count amount constant, and just ensures enough built-in reactivities at the Posterior circle that reloads.
Be arranged as 15 row * 15 with kilowatt pressurized water reactor nuclear power station 157 groups of assembly reactor cores to arrange, its reactor core adopts square cross section vertical prismatic shape assembly.In these 157 groups of assemblies, novel fuel assembly 72 groups, it uses the assembly of two kinds of uranium enrichments, and two kinds of uranium enrichments are respectively 4.45%, 4.2%; In reactor core, the assembly of burnup second circulation has 68 groups, and carrying out uranium enrichment when first circulation burnup enters to pile at it is 4.2% or 4.45%; In reactor core, the assembly of burnup the 3rd circulation has 16 groups, carries out uranium enrichment when first circulation burnup enters to pile be similarly 4.45% at it; Separately employ one group of assembly as center element.For with a collection of 72 groups of New Parents, when N=2, wherein 16 groups of assemblies draw off reactor core by after burnup three (N+1) circulation, the uranium enrichment of these 16 groups of assemblies when entering to pile first is 4.45%, all the other 56 groups of assemblies draw off reactor core after burnup two (N number of) circulation, and the uranium enrichment of these 56 groups of assemblies when entering to pile first is 4.2%.
In the cross-sectional view of the whole reactor cores 1/4th shown in Fig. 2, for New Parent, part New Parent be arranged on pressurized water reactor core with upper/lower positions: B08, B09, C09, D08, D10, D12, E09, E11, F10, F12, G09, G11, G13, G14, H12, H14, and the uranium enrichment of the New Parent of these positions when entering to pile first is 4.2%; Remainder New Parent be arranged on pressurized water reactor core with upper/lower positions: B10, C11, E13, F14, and the uranium enrichment of New Parent when entering to pile first of these positions is 4.45%.Will be understood that the arrangement of whole reactor core is 1/4 Rotational Symmetry by above-mentioned position.
Implement this technical scheme, after New Parent uses two kinds of enrichment assemblies, comparatively low enrichment can be used to the assembly of the less circulation of burnup, reduce fuel cost; And, can be reduced it and remain uranium enrichment when drawing off reactor core, and improve fuel service efficiency.
Preferably, also can add burnable poison in New Parent, such as, be 8,20 and 24 gadolinium bar fuel assemblies with burnable poison assembly, and the gadolinia fuel rod in assembly, its pellet is sintered by U02-Gd203 Homogeneous phase mixing and forms.
The foregoing is only the preferred embodiments of the present invention, be not limited to the present invention, for a person skilled in the art, the present invention can have various change, combination and change.Within the spirit and principles in the present invention all, any amendment done, equivalent replacement, improvement etc., all should be included within right of the present invention.
Claims (10)
1. the New Parent of a pressurized water reactor core reloads stowage, it is characterized in that, load the assembly of burnup that a collection of New Parent draws off same quantity simultaneously, for the New Parent with a collection of loading, wherein a part of New Parent will draw off reactor core after the N number of circulation of burnup in reactor core, remainder New Parent will draw off reactor core after burnup N+1 circulation in reactor core, wherein, N is natural number, and the uranium enrichment of described a part of New Parent when entering to pile first is lower than the uranium enrichment of described remainder New Parent when entering to pile first.
2. the New Parent of pressurized water reactor core according to claim 1 reloads stowage, and it is characterized in that, described N is 2.
3. the New Parent of pressurized water reactor core according to claim 2 reloads stowage, and it is characterized in that, the uranium enrichment of described a part of New Parent when entering to pile first is 4.2%, and the uranium enrichment of described remainder New Parent when entering to pile first is 4.45%.
4. the New Parent of pressurized water reactor core according to claim 1 reloads stowage, it is characterized in that, in described New Parent, adds burnable poison.
5. the New Parent of pressurized water reactor core according to claim 1 reloads stowage, it is characterized in that, described a part of New Parent be arranged on pressurized water reactor core with upper/lower positions: B08, B09, C09, D08, D10, D12, E09, E11, F10, F12, G09, G11, G13, G14, H12, H14; Described remainder New Parent be arranged on pressurized water reactor core with upper/lower positions: B10, C11, E13, F14, and the arrangement of whole reactor core is 1/4 Rotational Symmetry by above-mentioned position.
6. a pressurized water reactor core, it is characterized in that, described pressurized water reactor core is equipped with a collection of New Parent, wherein a part of New Parent will draw off reactor core after the N number of circulation of burnup in reactor core, remainder New Parent will draw off reactor core after burnup N+1 circulation in reactor core, and wherein, N is natural number, and the uranium enrichment of described a part of New Parent when entering to pile first is lower than the uranium enrichment of described remainder New Parent when entering to pile first.
7. pressurized water reactor core according to claim 6, is characterized in that, described N is 2.
8. pressurized water reactor core according to claim 7, is characterized in that, the uranium enrichment of described a part of New Parent when entering to pile first is 4.2%, and the uranium enrichment of described remainder New Parent when entering to pile first is 4.45%.
9. pressurized water reactor core according to claim 6, is characterized in that, described New Parent includes burnable poison.
10. pressurized water reactor core according to claim 6, it is characterized in that, described a part of New Parent be arranged on pressurized water reactor core with upper/lower positions: B08, B09, C09, D08, D10, D12, E09, E11, F10, F12, G09, G11, G13, G14, H12, H14; Described remainder New Parent be arranged on pressurized water reactor core with upper/lower positions: B10, C11, E13, F14, and the arrangement of whole reactor core is 1/4 Rotational Symmetry by above-mentioned position.
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| CN103151084B true CN103151084B (en) | 2016-02-03 |
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Families Citing this family (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103578588A (en) * | 2013-10-18 | 2014-02-12 | 中国核电工程有限公司 | Reactor core loading method for exchanging fuels of pressurized water reactor nuclear power plant after 18 months of balanced circulation |
| CN104680316B (en) * | 2015-02-12 | 2018-05-11 | 中国核电工程有限公司 | A kind of computational methods of nuclear power generating sets consumption uranium rate |
| CN107910077B (en) * | 2017-10-19 | 2021-08-24 | 中国核电工程有限公司 | VVER reactor type length-alternating balance cycle reactor core loading method |
| CN107977504B (en) * | 2017-11-28 | 2021-03-16 | 广东核电合营有限公司 | Asymmetric reactor core fuel management calculation method and device and terminal equipment |
| CN107863165B (en) * | 2017-12-08 | 2019-12-24 | 中国核动力研究设计院 | Method for loading 18-month refueling multi-cycle fuel of pressurized water reactor core |
| CN107863166B (en) * | 2017-12-08 | 2019-12-24 | 中国核动力研究设计院 | 18-month refueling loading method for pressurized water reactor first-cycle boron-containing reactor core |
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| EP1647994A2 (en) * | 2004-10-15 | 2006-04-19 | Westinghouse Electric Company LLC | First core fuel assembly configuration and method of implementing same |
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| JP2915200B2 (en) * | 1991-07-24 | 1999-07-05 | 株式会社日立製作所 | Fuel loading method and reactor core |
| US7636652B2 (en) * | 2003-10-06 | 2009-12-22 | Global Nuclear Fuel - Americas, Llc | Method and apparatus for facilitating recovery of nuclear fuel from a fuel pool |
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Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
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| US4451427A (en) * | 1978-02-03 | 1984-05-29 | Combustion Engineering, Inc. | In-core fuel management for nuclear reactor |
| EP1647994A2 (en) * | 2004-10-15 | 2006-04-19 | Westinghouse Electric Company LLC | First core fuel assembly configuration and method of implementing same |
| CN101241772A (en) * | 2007-09-26 | 2008-08-13 | 大亚湾核电运营管理有限责任公司 | 18-month feed replacement method for 1-million kW unit of China voltage water pile nucleus power station |
| CN102332315A (en) * | 2007-09-26 | 2012-01-25 | 大亚湾核电运营管理有限责任公司 | Refueling method for fuel assemblies of reactor core of PWR (pressurized water reactor) nuclear power plant |
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Address after: 518000 Guangdong province Futian District Shangbu Road West of the city of Shenzhen Shenzhen science and technology building 15 layer (1502-1504, 1506) Patentee after: CHINA NUCLEAR POWER TECHNOLOGY RESEARCH INSTITUTE Patentee after: China General Nuclear Power Corporation Address before: 518000 Guangdong, Futian District, Yitian Road, building A, block, building on the whole floor of A1301-1320 13 Patentee before: Zhongkehua Nuclear Power Technology Institute Co., Ltd. Patentee before: China Guangdong Nuclear Power Group Co., Ltd. |