摘要
为了对大型非能动先进压水堆安全设计以及相关事故分析程序的适宜性进行验证评估,针对非能动压水堆核电厂AP1000重要的设计基准事故之一——小破口失水事故(SBLOCA),基于其SBLOCA的现象过程识别与排序表(PIRT)中高重要度现象过程,采用系统性的分级双向比例模化(H2TS)方法,评估大型非能动先进堆芯冷却机理试验(ACME)台架模化验证AP1000核电厂SBLOCA事故的适宜性,进一步地,采用系统分析程序对AP1000小LOCA事故的模拟与部分ACME小破口事故验证试验的结果进行对比,从而初步评估了ACME对于AP1000小LOCA验证模拟的适宜性。
In order to verify the suitability of safety design of large passive advanced pressurized water reactor (PWR) and the reliability of related accident analysis program, the suitability of modeling the AP1000 under small break loss of coolant accident (SBLOCA) through the Advanced Core-cooling Mechanism Experiment (ACME) is evaluated in this paper. The process of SBLOCA with medium and high importance in the phenomena identification and ranking table (PIRT) is verified by means of hierarchical two-tiered scaling (H2TS). In addition, the system analysis program RELAP5 is used to scale the SBLOCA process of the AP1000. The scaling results are compared with ACME test results, to evaluate the suitability of using ACME to scale the SBLOCA of AP1000.
作者
卢霞
匡波
孔浩铮
刘鹏飞
LU Xia;KUANG Bo;KONG Haozheng;LIU Pengfei(School of Mechanical Engineering, Shanghai Jiao Tong University, Shanghai 200240, China)
出处
《应用科技》
CAS
2019年第5期80-87,共8页
Applied Science and Technology
