Refueling reactor core safety evaluation method

A technology of safety evaluation and stockpiling, applied in the field of safety evaluation of refueling core, to achieve the effects of expanding the scope of application, saving refueling design costs, and eliminating restrictive requirements

Active Publication Date: 2019-03-19
NUCLEAR POWER INSTITUTE OF CHINA
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Problems solved by technology

[0005] The purpose of the present invention is to provide a method for evaluating the safety of the refueling core, which solves the problem that the existing safety analysis method must require that the power distribution of the refueling core is similar to the reference safety analysis. The evaluation method of the present invention can avoid additional Under the premise of a large amount of analysis and evaluation work, it can effectively adapt to the flexibility of refueling core loading

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Embodiment

[0060] This embodiment is aimed at the safety evaluation of the second cycle refueling of Unit 1 of Changjiang Nuclear Power Plant in Hainan, and the specific safety evaluation method used for this refueling is introduced below. This paper mainly introduces the verification methods of critical safety parameters specifically implemented in the safety assessment, including general critical safety parameters, special critical safety parameters for specific accidents, and fuel assembly performance verification:

[0061] 1), general key safety parameters

[0062] ─Kinetic parameters

[0063] (1) The minimum and maximum values ​​of moderator density coefficient

[0064] The moderator density coefficient takes into account a calculation uncertainty of 3.6 pcm / °C. The minimum moderator density coefficient is calculated at the beginning of the life, and the maximum moderator density coefficient is calculated at the end of the life.

[0065] (2) Minimum and maximum values ​​of Dopple...

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Abstract

The invention discloses a refueling reactor core safety evaluation method. The safety evaluation method comprises the following steps: 1) obtaining universal key safety parameters; 2) obtaining special key safety parameters for a specific accident; 3) comparing the obtained general key safety parameters, the obtained special key safety parameters for the specific accident and input parameters usedfor reference safety analysis; and 4) performing fuel assembly performance verification. According to the method, on the basis of a traditional refueling reactor core safety evaluation method, the definition, selection criteria and range of key safety parameters are expanded, analysis modules specifically constructed in safety evaluation are reasonably designed, the limitation requirement for refueling reactor core power distribution is eliminated, and the application range of reference safety analysis is effectively expanded. The conclusion that the refueling reactor core meets the final safety analysis report can be proved from the perspective of reactor physics and thermotechnical hydraulics only through normal refueling reactor core safety evaluation work.

Description

technical field [0001] The invention relates to the technical field of nuclear power, in particular to a method for evaluating the safety of a refueling core. Background technique [0002] The refueling design of PWR nuclear power plants is a long-term and periodic important design work for active nuclear power plants. It mainly gives the loading scheme of the refueling core from the perspective of reactor physics and thermohydraulics, and according to the loading scheme, the theoretical prediction results of the main parameters of the nuclear reactor under the start-up, operation and shutdown conditions of the power plant within the cycle length are carried out to guide The power plant is running. Among them, the safety of the refueling core loading scheme is confirmed through the refueling safety evaluation, which is of great significance to the normal and safe operation of the nuclear power plant in a refueling cycle. [0003] The purpose of the refueling safety evaluat...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06Q10/06
CPCG06Q10/0639
Inventor 刘同先于颖锐李天涯肖鹏秦雪谢运利甯忠豪巨海涛汪量子吴文斌
Owner NUCLEAR POWER INSTITUTE OF CHINA
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