国内先进压水堆核电厂快速冷却功能首堆试验研究

Research on FPOT Fast Cool-down Function of Advanced PWR

快速冷却功能是我国自主三代核电技术所采用的一项新设计特性。其作用是在事故工况下,由安注信号触发大气排放阀的开启并自动调节,从而对反应堆冷却剂系统实施快速冷却,确保中压安注尽快注入。为验证快速冷却功能的正确性和与设计的符合性,经研究需开展调试首堆试验。该文描述了国内先进压水堆核电厂快速冷却功能首堆试验的实施方案和设计方法,以确保调试工作高效有序的开展,并为机组后续的安全稳定运行提供有力保障。与此同时,快速冷却功能首堆试验的结果也可用于同系列堆型的设计优化、调试、维修和运行等工作。

Advanced PWR is a third-generation advanced technology 1000 MWe-class pressurized water reactor developed by China National Nuclear Corporation.As one of the new design features of advanced PWR,fast cool-down function is to trigger the opening and the follow up controlling of the atmospheric discharge valve by the safety injection signal under the accident condition.It needs to carry out the FPOT(First Plant Only Tests)to verify the correctness of the fast cool-down function and compliance with the design.This paper researches the advanced PWR fast cool-down function FPOT implementation project and design methodology,which not only ensures the commissioning efficiency and arrangement,but also guarantees the safety operation.Meanwhile the FPOT results could be used for design optimization,commissioning,maintenance and operation of advanced PWR follow-up units.