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
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[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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