| 多群输运-燃耗耦合蒙特卡罗计算 |
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| 引用本文： | 邓力,谢仲生,李树.多群输运-燃耗耦合蒙特卡罗计算[J].计算物理,2003,20(1):65-70. |
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| 作者姓名： | 邓力 谢仲生 李树 |
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| 作者单位： | 1. 北京应用物理与计算数学研究所计算物理实验室,北京,100088
2. 西安交通大学核能科学工程系,陕西,西安,710049 |
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| 基金项目： | SupportedbytheScienceFoundationofChinaAcademyofEngineeringPhysicsundertheGrantNo .2 0 0 10 660 |
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| 摘 要： | 介绍了三维多群中子输运-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，使用多群截面为模拟临界实验堆和高通量工程实验堆，取得与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。
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| 关 键 词： | 耦合 计算 三维多群 P3近似 蒙特卡罗 中子输运 燃耗 核反应堆 |
Multigroup Monte Carlo Calculation Coupled of Transport and Burnup |
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| Abstract.Multigroup Monte Carlo Calculation Coupled of Transport and Burnup[J].Chinese Journal of Computational Physics,2003,20(1):65-70. |
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| Authors: | Abstract |
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| Abstract: | 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. |
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| Keywords: | D multigroup P\-3 approximation Monte Carlo neutron transport burnup |
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