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MELCOR程序在HTGR事故分析中的最新进展
引用本文:周克峰,陈召林,冯进军,高强,李茂林,刘运陶.MELCOR程序在HTGR事故分析中的最新进展[J].核安全,2013(3):62-67.
作者姓名:周克峰  陈召林  冯进军  高强  李茂林  刘运陶
作者单位:环境保护部核与辐射安全中心,北京100082
摘    要:MELCOR程序是美国NRC在安全评审中使用的一体化系统分析程序,早期主要用于轻水堆严重事故分析。近年来,该程序逐渐用于高温气冷堆的石墨腐蚀、裂变产物行为和石墨粉尘等物理现象方面的研究。本文介绍了在最新版本的MELCOR2.1程序中,针对高温气冷堆特点所进行的扩展和开发,以及MELCOR程序在高温气冷堆(HTGR)事故分析中的计算流程。

关 键 词:MELCOR  2  1  高温气冷堆  超设计基准事故  新进展

Latest Progress of HTGR Accident Analysis in MELCOR
ZHOU Kefeng,CHEN Zhaolin,FENG Jinjun,GAO Qiang,LI Maolin,LIU Yuntao.Latest Progress of HTGR Accident Analysis in MELCOR[J].Nuclear Safety,2013(3):62-67.
Authors:ZHOU Kefeng  CHEN Zhaolin  FENG Jinjun  GAO Qiang  LI Maolin  LIU Yuntao
Affiliation:(Nuclear and Radiation Safety Center, MEP, Beijing 100082, China)
Abstract:MELCOR code is an integrated system analysis code used by U. S. NRC for the nuclear safety review. In the early days, the code was mainly used for hght water reactor (LWR) severe accident analy- sis. And in recent years, the code has been used in the research of high temperature gas-cooled reactor (HTGR) physical phenomena, including graphite corrosion, the behavior of fission products (FP) and graphite dust. Code extension and development was introduced according to the characteristics of HTGR in the latest edition of MELCOR code, MELCOR 2.1, and MELCOR code calculation process for HTGR was also introduced.
Keywords:MELCOR 2  1  HTGR  beyond design basis accident  the latest development
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