Pressurized water reactor nuclear power plant mega-kilowatt unit complete low neutron escape advanced one-quarter refueling method and safety analysis system thereof

A pressurized water reactor nuclear power plant, safety analysis technology, applied in the field of improvement of nuclear reactor core refueling method and nuclear reactor safety analysis system, can solve the problems of low fuel utilization rate, high neutron leakage rate, etc., to improve safety and economy Effect

Active Publication Date: 2011-05-11
LINGAO NUCLEAR POWER +2
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0007] Aiming at the above-mentioned defects of the prior art, the present invention solves the problems of high ne...

Method used

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  • Pressurized water reactor nuclear power plant mega-kilowatt unit complete low neutron escape advanced one-quarter refueling method and safety analysis system thereof
  • Pressurized water reactor nuclear power plant mega-kilowatt unit complete low neutron escape advanced one-quarter refueling method and safety analysis system thereof
  • Pressurized water reactor nuclear power plant mega-kilowatt unit complete low neutron escape advanced one-quarter refueling method and safety analysis system thereof

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Embodiment 1

[0053] The schematic diagram of the partial layout of the core for the complete low neutron leakage 1 / 4 refueling in the first embodiment is as follows figure 2 As shown, it is 1 / 4 of the overall layout schematic diagram, in which there are 40 groups of new fuel assemblies with an enrichment degree of 4.2%. figure 2 in, symbol Indicates a new fuel assembly with an enrichment degree of 4.2%, a total of 40 groups; Indicates that the enrichment degree is 4.2% of the second cycle of refueling components, a total of 40 groups; Indicates that the enrichment degree is 4.2% of the third cycle of refueling components, a total of 40 groups; Represents the fourth cycle of refueling components with an enrichment degree of 4.2%, and there are 37 groups in total.

[0054] Its markings H09, F08, etc. are the position codes for recording the source of components when unloading, which can be changed according to different loading schemes. The assembly positions marked 0, 4, and 8 are...

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Abstract

The invention relates to a pressurized water reactor nuclear power plant mega-kilowatt unit complete low neutron escape advanced one-quarter refueling method and a safety analysis system thereof. The pressurized water reactor nuclear power plant mega-kilowatt unit complete low neutron escape advanced one-quarter refueling method comprises: replacing one quarter of new fuel components, namely 32 to 48 components, in each fuel cycle; and putting the new fuel components in the reactor core of the reactor initially, wherein the inside of the reactor core refers to the place inside a secondary outer ring of the reaction core including the secondary outer ring. When the complete low neutron escape advanced one-quarter refueling method is adopted, the safety and economy of the reactor core and fuel are improved considerably, the maximum fuel consumption of the fuel components can reach 57,000MWd/tU, fuel cost is saved and the service life of the pressure vessel of the reactor can be prolonged. Meanwhile, the safety analysis system of the invention can provide a necessary implementation condition for the complete low neutron escape advanced one-quarter refueling method and provides a necessary environment for the normal operation of the reactor which is arranged by the method.

Description

technical field [0001] The invention relates to the technical field of a nuclear reactor of a million-kilowatt unit of a pressurized water reactor nuclear power plant, and more specifically relates to an improvement on a nuclear reactor core refueling method and a nuclear reactor safety analysis system. Background technique [0002] In nuclear power plants, the cost of nuclear fuel usually exceeds the sum of operating and maintenance costs. Therefore, advanced fuel management measures must be implemented to improve the utilization rate and economy of nuclear fuel, increase the full power operation capacity of the power plant, reduce the core neutron leakage rate, and thus prolong the life of the pressure vessel. [0003] Taking Ling Ao Nuclear Power Plant of Guangdong Nuclear Power Group Co., Ltd. as an example, the original core design scheme is a backward management mode of high-energy leakage fuel, and 1 / 3 of the core (about 52-56 groups) of new fuel is replaced every yea...

Claims

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Application Information

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IPC IPC(8): G21C19/00G21D3/04
CPCY02E30/00Y02E30/30
Inventor 高立刚肖岷张洪李雷韩庆浩戴忠华李晓明马仓
Owner LINGAO NUCLEAR POWER
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