CN1328730C - Reactor core loading method of pressurized water reactor nuclear power station reactor - Google Patents
Reactor core loading method of pressurized water reactor nuclear power station reactor Download PDFInfo
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- CN1328730C CN1328730C CNB2004100524840A CN200410052484A CN1328730C CN 1328730 C CN1328730 C CN 1328730C CN B2004100524840 A CNB2004100524840 A CN B2004100524840A CN 200410052484 A CN200410052484 A CN 200410052484A CN 1328730 C CN1328730 C CN 1328730C
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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
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Abstract
The present invention discloses a reactor core loading method of a pressurized water reactor nuclear power station reactor, which solves the problems of large neutron leakage and short length of cycle existing in the traditional reactor cores. The present invention has the technical scheme that assemblies which need to be updated are stacked in the internal rings of reactor cores; combusted assemblies are laid on the periphery; the combusted assemblies stacked on the periphery are combined according to the match of combustion colors; the reactor cores are 1/4 symmetrical. The present invention has the advantages that the service lives of reactor cores are prolonged, the power distribution of reactor cores is easy to expand flat, the power peak factors of reactor cores are low, the service lives of pressure vessels are prolonged, etc.
Description
Technical field
The present invention relates to a kind of nuclear power station nuclear and should pile technology, relate in particular to a kind of pressurized-water reactor nuclear power plant reactor core stowage.
Background technology
In the design of reactor core loading pattern, what traditional nuclear power station adopted all is the OUT-IN load mode, and promptly New Parent is arranged in the reactor core periphery, and other burnup is crossed assembly by burnup depth matched combined, be assemblied in the reactor core inner lane, and will guarantee 1/4 symmetry of reactor core.New Parent is arranged in reactor core periphery (as shown in Figure 1), leans on inner lane much bigger because it is revealed in the periphery than being arranged in reactor core, then the distribute power of reactor core is easy to flatten, and its power peak factor correspondingly will be much lower.
Like this, because neutron leakage is bigger, length of the cycle is shorter, and it is not fine that fuel utilizes economy.
Summary of the invention
In order to overcome the deficiency of existing stowage, the invention provides the pressurized-water reactor nuclear power plant reactor core stowage that a kind of length of the cycle is long, neutron leakage is lower.
For realizing purpose of the present invention, the technical solution adopted in the present invention is: a kind of pressurized-water reactor nuclear power plant reactor core stowage is provided, the New Parent that needs are upgraded piles up the reactor core inner lane, burnup is crossed assembly and is placed on the periphery, add burnable poison in the described New Parent, the described burnable poison assembly that has is a fuel assembly with 8,20 and 24 gadolinium rods.
Burnup is crossed assembly and New Parent by burnup depth matched combined.
Gadolinia fuel rod in the assembly, its pellet is formed by the even mixed sintering of U02-Gd203.
The Cd203 percentage by weight is 8% in the pellet, and the U235 percentage by weight is 2.5%.
After adopting said structure, promptly New Parent be arranged in reactor core by behind the inner lane than common OUT-IN load mode, its length of the cycle is much longer.
New Parent is placed on reactor core by inner lane, burnup is crossed assembly and is placed on the periphery, have burnable poison assembly and be fuel assembly with 8,20 and 24 gadolinium rods, then reactor core outer boundary place neutron flux is lower, like this, neutron leakage reduces greatly, and the neutron utilization ratio improves greatly, finally can make the assembly burnup burn deeplyer, produce more energy.Simultaneously, adopt the low load mode of leaking, both helped the raising of neutron utilization ratio, can reduce the pressure vessel neutron fluence again, prolong its serviceable life.New Parent is arranged in reactor core by inner lane, because New Parent is reactive higher, again little by the inner lane leakage at reactor core, then power peak factor all concentrates on the New Parent, can be very high.
After adopting above-mentioned stowage, the peripheral assembly relative power drops to about about 0.3-0.5 from the about 0.6-0.8 under the present out-in mode, and neutron is revealed greatly and reduced, and the pressure vessel neutron fluence also greatly reduces, it is estimated that the pressure vessel life-span correspondingly can extend to 50 years from about 40 years.
Description of drawings
Fig. 1 is a prior art pressurized-water reactor nuclear power plant reactor core Stowage Plane;
Fig. 2 is the structural representation that the present invention 1/4 loads.
Embodiment
Design of the present invention is that the assembly that needs upgrade is piled up the reactor core inner lane, and outermost is loaded burnup and crossed assembly.
In the loading process of whole reactor core, the inner lane that the burnup that can load in the periphery be crossed assembly loads new assembly, enters to adopt burnup to cross assembly and New Parent by burnup depth matched combined, the assembly cross arrangement that burn-up level is different in the inner lane again.
It is a combination with 1/4 reactor core that the assembly of reactor core of the present invention loads arrangement mode, and whole reactor core is made up of four above-mentioned reactor cores, and is 1/4 symmetry arrangement.
In order to make the assembly burnup burn deeplyer, produce more energy, can in New Parent, add and use Gd203 dispersivity burnable poison.
The described burnable poison assembly that has can be the fuel assembly with 8,20 and 24 gadolinium rods.
Gadolinia fuel rod in the assembly, its pellet is formed by the even mixed sintering of U02-Gd203, and wherein the Cd203 percentage by weight is 8% in the pellet, and the U235 percentage by weight is 2.5%.
Fig. 2 illustrates the structural representation of 1/ village loading of one embodiment of the invention, among the figure
(48 groups) (52 groups) (57 groups)
N:Gd rod number
Slogan banner is by the arrangement of outer ring to inner lane by A-H, perpendicular mark 15-08 successively among this figure.
The peripheral coordinate 14 of reactor core and E, 13 with D, 12 with C, 11 and the point of crossing of B pile and put burnup and enter 52 groups of Gd rod assemblys of the second round-robin band, then at the new assembly of its inner lane heap pendulum, and sit around outside mark 13 and E, the 12 new assemblies of putting with C point of crossing heap with D, 11 contain the fuel assembly with 8 gadolinium rods, wherein in this new assembly 48 groups of Gd rods, arrange heap pendulum burnup to inner lane again and enter 57 groups of Gd rod assemblys of the 3rd round-robin band, but the mark 14 of sitting around is outside put burnup with G, 09 with the point of crossing heap of B and entered 52 groups of Gd rod assemblys of the second round-robin band.
Inwardly arrange successively by circle time then:
These circle China and foreign countries sit around mark 14 and H, 13 with G, 11 with E, 09 and C, 08 and the point of crossing of B pile and put burnup and enter 52 groups of Cd rod assemblys of the second round-robin band, and the 10 new assemblies of putting with the point of crossing of F heap with D, 12 contain the fuel assembly with 8 gadolinium rods, wherein are 48 groups of Cd rods in this new assembly;
These circle China and foreign countries sit around mark 13 and H, 12 with G, 11 with F, 10 and E, 09 and D, 08 and the point of crossing of C pile and put the assembly that burnup enters 57 groups of Cd rods of the 3rd round-robin band;
These circle China and foreign countries sit around mark 12 and H, 10 with F, 08 with the point of crossing heap pendulum of D new be with 48 groups of Gd rod assemblys, and 11 with G, 09 and the point of crossing of E pile the burnup of putting and enter 52 groups of Cd rod assemblys of the second round-robin band;
This circle heap pendulum burnup enters the assembly of 57 groups of Gd rods of the 3rd round-robin band;
These circle China and foreign countries sit around mark 10 and H, 8 with the point of crossing heap pendulum of F new be with 48 groups of Gd rod assemblys, and 09 burnup of putting with the point of crossing heap of G enters 57 groups of Cd rod assemblys of the 3rd round-robin band;
The burnup of this circle heap pendulum enters 52 groups of Gd rod assemblys of the second round-robin band; This circle burnup enters 57 groups of Gd rod assemblys of the 3rd round-robin band; Stating structure more than the whole reactor core is the unit, and is 1/4 symmetry arrangement.
Claims (4)
1, a kind of pressurized-water reactor nuclear power plant reactor core stowage, the New Parent that needs are upgraded piles up the reactor core inner lane, burnup is crossed assembly and is placed on the periphery, add burnable poison in the described New Parent, it is characterized in that: the described burnable poison assembly that has is a fuel assembly with 8,20 and 24 gadolinium rods.
2. pressurized-water reactor nuclear power plant reactor core stowage as claimed in claim 1 is characterized in that: burnup is crossed assembly and New Parent by burnup depth matched combined.
3, pressurized-water reactor nuclear power plant reactor core stowage as claimed in claim 1 or 2 is characterized in that: the gadolinia fuel rod in the assembly, its pellet is formed by the even mixed sintering of U02-Gd203.
4, pressurized-water reactor nuclear power plant reactor core stowage as claimed in claim 3, it is characterized in that: the Gd203 percentage by weight is 8% in the pellet, the U235 percentage by weight is 2.5%.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CNB2004100524840A CN1328730C (en) | 2004-12-03 | 2004-12-03 | Reactor core loading method of pressurized water reactor nuclear power station reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CNB2004100524840A CN1328730C (en) | 2004-12-03 | 2004-12-03 | Reactor core loading method of pressurized water reactor nuclear power station reactor |
Publications (2)
| Publication Number | Publication Date |
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| CN1783352A CN1783352A (en) | 2006-06-07 |
| CN1328730C true CN1328730C (en) | 2007-07-25 |
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| Application Number | Title | Priority Date | Filing Date |
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| CNB2004100524840A Expired - Fee Related CN1328730C (en) | 2004-12-03 | 2004-12-03 | Reactor core loading method of pressurized water reactor nuclear power station reactor |
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Families Citing this family (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101206930B (en) * | 2006-12-22 | 2011-06-15 | 深圳中广核工程设计有限公司 | Method for cycle using multi-stack combined nuclear fuel |
| CN101241772B (en) * | 2007-09-26 | 2011-07-27 | 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 PWR nuclear power station |
| CN101847450B (en) * | 2009-05-27 | 2012-10-03 | 中广核工程有限公司 | Associated disposition method of fuel for nuclear power plant |
| CN102054538B (en) * | 2009-10-30 | 2013-07-17 | 中国广东核电集团有限公司 | Pressurized water reactor nuclear power plant mega-kilowatt unit complete low neutron escape advanced one-quarter refueling method and safety analysis system thereof |
| 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 |
| CN108053892B (en) * | 2017-12-08 | 2019-07-16 | 中国核动力研究设计院 | A kind of naval reactor reactivity control method |
| CN109801718B (en) * | 2018-12-06 | 2020-12-22 | 华南理工大学 | Intrinsic safety pressurized water reactor with movable and separable reactor core |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1229514A (en) * | 1996-09-04 | 1999-09-22 | 株式会社日立制作所 | Initial loading core |
| JP2002286887A (en) * | 2001-03-27 | 2002-10-03 | Nuclear Fuel Ind Ltd | Fuel operation method for pressurized water reactor, and pressurized water reactor core |
| CN1527328A (en) * | 2003-02-25 | 2004-09-08 | 西屋电气有限责任公司 | Method for establishing nuclear reactor reactor core fuel assembly loading mode |
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- 2004-12-03 CN CNB2004100524840A patent/CN1328730C/en not_active Expired - Fee Related
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1229514A (en) * | 1996-09-04 | 1999-09-22 | 株式会社日立制作所 | Initial loading core |
| JP2002286887A (en) * | 2001-03-27 | 2002-10-03 | Nuclear Fuel Ind Ltd | Fuel operation method for pressurized water reactor, and pressurized water reactor core |
| CN1527328A (en) * | 2003-02-25 | 2004-09-08 | 西屋电气有限责任公司 | Method for establishing nuclear reactor reactor core fuel assembly loading mode |
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| CN1783352A (en) | 2006-06-07 |
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Owner name: LING'AO NUCLEAR POWER CO., LTD. Free format text: FORMER OWNER: DAYABAY NUCLEAR POWER OPERATIONS AND MANAGEMENT CO., LTD. (DNMC) Effective date: 20091016 |
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Effective date of registration: 20091016 Address after: 18 floor, nuclear power building, Shennan Middle Road, Futian District, Shenzhen, Guangdong, zip code: 518000 Co-patentee after: DAYABAY NUCLEAR POWER OPERATIONS AND MANAGEMENT Co.,Ltd. Patentee after: LING'AO NUCLEAR POWER Co.,Ltd. Address before: Guangdong city of Shenzhen province Futian District science and technology building, Shangbu road 18 zip code: 518031 Patentee before: DAYABAY NUCLEAR POWER OPERATIONS AND MANAGEMENT Co.,Ltd. |
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Granted publication date: 20070725 Termination date: 20211203 |
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| CF01 | Termination of patent right due to non-payment of annual fee |