AP1000全失流事故DNBR计算分析  

AP1000 DNBR Calculation and Analysis of Complete Loss of Flow Accident

作　　者：黄树亮 冯进军[2] 陈巧艳 肖红[2] 

机构地区：[1]中国核电工程有限公司,北京100840 [2]环境保护部核与辐射安全中心,北京100082

出　　处：《核动力工程》2015年第2期33-36,共4页Nuclear Power Engineering

摘　　要：AP1000反应堆冷却剂强迫流动全部丧失事故(简称全失流事故)可能导致堆芯发生偏离泡核沸腾(DNB)。使用美国核安全管制委员会(NRC)的TRACE程序和法国子通道分析程序FLICAⅢ-F,对AP1000电厂系统和堆芯进行建模,使用TRACE程序给出的全失流事故瞬态参数作为FLICAⅢ-F程序的输入条件,进行全失流事故DNB分析。计算结果表明:在瞬态过程中,堆芯内偏离泡核沸腾比(DNBR)数值始终高于安全分析限值,满足DNB设计基准。通过与安全分析报告中的计算数据进行对比,证明本文用TRACE和FLICAⅢ-F程序建立的DNB分析计算模型是合理的,能够用于AP1000电厂的工程设计。The accident of complete loss of forced reactor coolant flow in AP1000 plant may cause the phenomenon of departure from nucleate boiling（DNB） in the reactor core. This paper uses the TRACE code of US NRC and FLICA Ⅲ-F sub-channel code of France to establish the model of the AP1000 reactor system and core, and uses the transient parameters given by the code of TRACE as the input parameters of FLICA Ⅲ-F, and calculates and analyzes the transient DNB of complete loss of flow accident. The calculate result shows that in the transient the DNBR value in the reactor core is always higher than the safety analysis limit, thus it satisfies the DNB design criterion. By comparing the result with the value from the safety analysis report, it demonstrates that the system and DNB analysis model by TRACE and FLICA Ⅲ-F code in this paper is reasonable which is available in the AP1000 project design.

关 键 词：全失流 TRACE FLICAⅢ-F DNBR 子通道 

分 类 号：TL364.4[核科学技术—核技术及应用]