摘要
介绍三维多群中子输运 燃耗耦合P3近似蒙特卡罗程序MCMG BURN .该程序是在连续截面蒙特卡罗程序MCNP和反应堆栅元均匀化程序WIMS基础上发展而来的 .使用多群截面库模拟临界实验堆和高通量工程实验堆 ,取得了与MCNP和实验一致的结果 .MCMG BURN具有与MCNP相同的精度 ,但计算时间较MCNP要少得多 .
A 3\|D multigroup P\-3 approximation Monte Carlo code MCMG\|BURN is developed by coupling the neutron transport and burnup.MCMG\|BURN code is based on the continuous\|energy cross\|section Monte Carlo code MCNP and the lattice homogeneous code WIMS.It uses the multigroup cross\|section libraries to simulate the critical test reactors and HFETR(High Flux Engineering Test Reactor).The agreement results with the MCNP results and experiments are achieved.The MCMG\|BURN code is at almost the same precision with the MCNP code while requiring considerably less computing time.
出处
《计算物理》
CSCD
北大核心
2003年第1期65-70,共6页
Chinese Journal of Computational Physics
基金
SupportedbytheScienceFoundationofChinaAcademyofEngineeringPhysicsundertheGrantNo .2 0 0 10 660
