摘要
本文利用反应堆热工水力软件TRACE对三回路国产先进压水堆发生小破口失水事故进行模拟计算,得到事故过程中反应堆系统压力、水位、破口流量的变化和安注系统的投入情况,将计算结果与CATHARE程序的计算结果进行对比、分析和讨论,两程序计算结果在趋势上较符合,验证了TRACE程序在计算小破口事故的准确性。
In this paper SB-LOCA accident calculation of three-loop Domestic Advanced PWR is carried out by the reactor thermal hydraulic code of TRACE,the results include reactor system pressure, core water level, break flow rate and safety injection system operating condition. Further the calculation results are compared with the ones got with CATHARE code to make verification that whether the results we got are correct.
出处
《核科学与工程》
CSCD
北大核心
2017年第6期1026-1032,共7页
Nuclear Science and Engineering
基金
大型先进压水堆及高温气冷堆电站国家科技重大专项:CAP1400安全审评关键技术研究(2013ZX06002001)
大型先进压水堆及高温气冷堆电站国家科技重大专项:CAP1400核安全监管重要试验验证(2015ZX06002007)
