压水堆核电厂失水事故后安全壳内产氢量计算研究  

Calculation Research of Hydrogen Production Amount in Containment after LOCAL in PWR Nuclear Power Plants

作　　者：胡建军[1] 

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610041

出　　处：《核动力工程》2013年第S1期95-98,共4页Nuclear Power Engineering

摘　　要：采用ORIGEN2程序对压水堆核电厂失水事故工况下堆芯区和地坑区氢气的产生量进行计算,以合理减少安全壳内可燃气体的控制设计评价的保守性。通过冷却剂的辐照分解产氢以及其他相关计算模型,对600MW(电功率)级压水堆核电厂失水事故工况下的氢气产生量进行计算。计算结果表明原评价结果过于保守,在核电厂失水事故后仍有充分的时间准备投入安全壳内氢气复合器。The ORIGEN2 code is adopted to calculate the amount of hydrogen production in the core and sump region after LOCAL in PWR nuclear power plants,to reduce the conservatism for the design evaluation of the combustible gas control in the containment.The calculation model of radiolytic decomposition coolant and other related calculation model are used to calculate the amount of hydrogen production after LOCA in a 600MW PWR nuclear power plant,and the results show that over conservatism of the original evaluation,and there still exists abundant time to prepare and startup the hydrogen recombiners in the containment after LOCAL.

关 键 词：压水堆核电厂 失水事故 ORIGEN2 产氢量分析 

分 类 号：TM623[电气工程—电力系统及自动化]