AP1000和CPR1000核电机组SGTR事故释放源项比较分析  

Comparison of SGTR Accident Source Terms for AP1000 and CPR1000

作　　者：陈洋[1] 丁四中[1] 上官志洪[1] 

机构地区：[1]苏州热工研究院有限公司,江苏苏州215004

出　　处：《辐射防护》2011年第3期129-133,167,共6页Radiation Protection

摘　　要：在对压水堆核电厂蒸汽发生器传热管断裂(SGTR)事故进程分析的基础上,确定了SGTR事故释放源项的计算模型,并以此计算模型对设计方提供的AP1000和CPR1000 SGTR事故释放源项进行了复核。针对两种核电机组SGTR事故的源项计算假设、源项大小进行了对比分析,提出了在评估SGTR事故放射性后果时需要关注的问题和解决措施。Based on the analysis of process of the SGTR accident, a calculation model was established and the SGTR source terms of AP1000 and CPR1000 were checked in this paper. A comparison of the SGTR source terms for AP1000 and CPR1000 was made. Some problems were addressed in evaluating radioactive consequences of SGTR accident.

关 键 词：核电厂 SGTR事故源项 AP1000 CPR1000 计算模型 

分 类 号：TM623.3[电气工程—电力系统及自动化]