基于CIAE实验对RELAP5程序的评价  

An Evaluation of RELAP5 Based on the CIAE Experiments

作　　者：陈玉宙[1] 杨春生[1] 邹凌[1] 

机构地区：[1]中国原子能科学研究院,北京102413

出　　处：《核动力工程》2003年第S2期64-69,共6页Nuclear Power Engineering

摘　　要：RELAP5程序是进行反应堆安全分析的重要工具,程序的评价和改进是世界各国核安全研究中的一个重要课题。中国原子能科学研究院围绕对反应堆事故后果有重要影响的一些热工水力现象开展了大量实验研究,包括膜态沸腾传热、临界热流密度和摩擦压降,并在此基础上对RELAP5程序模型进行评价,表明了模型的缺陷,并在一定条件下计算存在较大不确定性。The thermal-hydraulic system code RELAP5 is widely applied in nuclear safety analyses. The verification and validation of the code is an important subject in the research of nuclear safety over the world. A great number of experiments have been carried out in China Institute of Atomic Energy (CIAE), including the film boiling, critical heat flux and frictional pressure drop, which are most concerned in the nuclear reactor accident. Based on the CIAE experimental data, an evaluation of the code has been performed, revealing that the deficiencies in the models of the code and the uncertainty in prediction of the code is appreciable.

关 键 词：RELAP5程序 膜态沸腾 临界热流密度 摩擦阻力 

分 类 号：TL364[核科学技术—核技术及应用] TL33