RELAP5/MOD3.3程序对非能动核电厂小破口失水事故的适用性研究

Applicability Research of RELAP5/MOD3.3 for Small Break Loss of Coolant Accident of NPP With Passive Safety System

AP1000核电厂采用非能动堆芯冷却系统来缓解小破口失水事故(SBLOCA),缓解事故的理念是流动冷却。RELAP5/MOD3.3程序适用于传统核电厂SBLOCA研究,对于非能动电厂SBLOCA研究的适用性需重新研究与评估。本工作基于非能动电厂小破口失水事故的分析,结合RELAP5/MOD3.3的结构与模型,对其进行评估和改进。为验证改进后的RELAP5/MOD3.3的适用性,以AP1000小破口失水事故的验证试验台架APEX-1000为模拟对象,分析模拟DBA-02、NRC-05事故工况。分析结果表明,改进后的RELAP5/MOD3.3的计算结果与试验数据符合较好。

The passive core cooling system is used in AP 1000 to mitigate the small break loss of coolant accident （SBLOCA） .The RELAP5/MOD3.3 code is generally applicable to the traditional NPP SBLOCA research , but for the passive NPP SBLOCA , its applicability will need further study and evaluation . Based on the analysis of the important phenomenon of the SBLOCA of the passive NPP , the RELAP5/MOD3.3 code was assessed and modified . In order to verify the applicability of the modified RELAP5/MOD3.3 code ,the DBA-02 and NRC-05 cases of APEX-1000 which was the test facility for verifying AP1000 small break loss of coolant accident ,were simulated . It shows good agreement between the results of the modified RELAP5/MOD3.3 code and experiment data .