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作 者:刘宇生[1] 许超 胡健[1] 庄少欣[1] 房芳芳 Liu Yusheng;Xu Chao;Hu Jian;Zhuang Shaoxin;Fang Fangfang(Nuclear and Radiation Safety Center,MEP,Beijing,100086,China;State Nuclear Power Technology R&D Center,Beijing,102209,China)
机构地区:[1]环境保护部核与辐射安全中心,北京100086 [2]国核华清(北京)核电技术研发中心有限公司,北京102209
出 处:《核动力工程》2019年第3期97-102,共6页Nuclear Power Engineering
基 金:国家科技重大专项CAP1400核安全监管重要试验验证资助(2015ZX06002007-001)
摘 要:针对我国大型非能动堆芯冷却系统整体试验(ACME)台架开展的全厂断电(SBO)整体效应试验,利用Relap5程序进行了建模和数值模拟,并进行了参数的比对分析,结果表明:Relap5数值模型可较好地再现ACME台架SBO整体试验的主要事故进程,其事故序列、关键热工水力现象均与试验结果一致;对于堆芯与非能动余热排出换热器(PRHR HX)和堆芯补水箱(CMT)间的自然循环现象,Relap5计算的自然循环流量偏高,自然循环瞬态过程较试验过程偏快;对于主回路系统(RCS)瞬态压力和稳压器水位峰值,Relap5的计算结果是保守的,存在安全裕量。To study the performance characteristics of AP type passive nuclear power plant under typical station blackout(SBO)condition,numerical analyses are investigated based on the SBO integral tests conducted on the Advanced Core-cooling Mechanism Experiment(ACME)facility.The main parameters,which are obtained by establishing model with Relap5 code,are compared with that of SBO integral tests.The results show that the Relap5 model represents the major accident progress of ACME SBO tests well.The accidents chronology and key thermal hydraulic phenomena of post-calculations are consistent with that of tests.For natural circulation process between core and passive residual heat removal heat exchanger(PRHR HX),the calculated circulation rate is greater than that of tests,which results in a faster natural circulation process.The comparison analysis also shows that the results predicted by Relap5 are conservative for transient pressure of reactor coolant system(RCS)and maximum water level in pressurizer.There is a margin between numerical values and experimental values.
关 键 词:全厂断电(SBO) ACME台架 整体试验 非能动安全 RELAP5
分 类 号:TL333[核科学技术—核技术及应用]
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