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MELCOR 2.1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。
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.
出处
《核安全》
2013年第3期62-67,共6页
Nuclear Safety
