基准事故后AP1000安全壳响应分析简化模型研究  

A Simplified Model to Simulate AP1000 Containment Pressure Response during Design Basis Accidents

作　　者：王国栋[1] 汤微建 王喆[1,2] 张经瑜[1] 张迪[1] 倪陈宵[1] 韦胜杰[1] 王章立[1] 扈本学[1] 

机构地区：[1]上海核工程研究设计院,上海200233 [2]上海交通大学机械与动力工程学院,上海200240

出　　处：《核动力工程》2016年第3期163-168,共6页Nuclear Power Engineering

摘　　要：针对先进的百万千万级非能动型压水堆(AP1000),提出一种简化的设计基准事故(DBAs)后安全壳响应分析模型,并将该简化模型分析结果和WGOTHIC程序模拟结果进行比较和评价。研究表明:两者吻合良好,简化模型能很好地模拟AP1000安全壳系统的传热传质过程。A simplified model is developed to simulate the AP1000 containment pressurization under design basis accidents （DBAs）. The containment response has been performed by WGOTHIC code for comparison purpose. It shows a good agreement between the model and WGOTHIC code prediction results on containment heat and mass transfer process.

关 键 词：非能动安全壳冷却系统(PCS) WGOTHIC 先进的百万千万级非能动型压水堆(AP1000) 传热传质 压力响应 

分 类 号：TL364.3[核科学技术—核技术及应用]