Corium Spreading Analysis with THEMA Code for Nuclear Reactor

摘要：

THEMA is a computer code that models the thermo-hydraulics behavior of corium as it spreads over the surface of a core catcher. In this paper, after a brief introduction to THEMA code, a simulation on EPR geometry for corium spreading on the substrate of core catcher after reactor pit melt through will be described, and sensitivity analysis upon four parameters will also be given, and finally the comparison between results calculated by THEMA and the results used in EPR design will be performed and then the conclusion will be given.

关键词： EPR Corium Spreading

作者: Li Lan

作者单位: State Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China, Chengdu 610041, China

会议类型: 国际会议

会议名称: ISSNP2008、CSEPC、ISOFIC2008(第二届21世纪和谐核电系统国际会议、第四届电厂控制中认知系统工程方法国际会议暨第三届未来核电厂仪表与控制国际会议)

会议地点: 哈尔滨

会议语种:英文

页码: 252-255

在线出版日期: 2008-09-08（万方平台首次上网日期，不代表论文的发表时间）