摘要
采用最佳估算程序TRACE,模拟分析了某大功率非能动核电厂在中破口事故下的瞬态变化,绘制了冷却剂系统压力、自动卸压系统流量、冷却剂系统水装量等参数的变化曲线。在此基础上,根据M310电厂共性问题调研,选取泵延迟工况和小破口工况作为敏感性分析工况,同基准工况进行了比较与分析。结果表明:虽然不同的工况在某些时间段可能造成冷却剂系统水装量低于基准工况,但最小的冷却剂系统水装量均高于限值,没有出现堆芯裸露,验证了大功率非能动核电厂发生破口事故后的安全性。
Based on the best estimation program TRACE, this paper analyzes the transient changes under a me. dium-break accident of an high power passive nuclear power plant by simulation, and draws the corresponding curves of coolant system pressure, automatic-pressure-relief system flow, and coolant system water installa. tion. Based on this context, the pump delay condition and small size break condition are selected for sensitivity analysis and calculation to compare with the reference conditions according to the results of common issue in. vestigation of M310 nuclear power plants. The results show that although the primary circuit water capacity may sometimes be lower than the reference conditions under various conditions, the minimum water capacity is still above the limit with the core covered, and no core exposed. This result verifies the safety of high-power passive nuclear power plants after a break accident.
作者
庄少欣
王娅琦
孙微
贾斌
刘宇生
Zhuang Shaoxin;Wang Yaqi;Sun Wei;Jia Bin;Liu Yusheng(Nuclear and Radiation Safety Center, MEE, Beijing 100082, China;CNNC Engineering Consultation Co.,Ltd., Beijing 100048, China)
出处
《核安全》
2019年第4期63-69,共7页
Nuclear Safety
基金
国家科技重大专项——CAP1400核安全监管重要试验验证,项目编号:2015ZX06002007-001
