Development and Benchmark Calculation of Multigroup Monte Carlo Code MCMG

JIANG Xiaofeng; LUAN Xingfeng; DENG Li

Mar. 2007

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JIANG Xiaofeng, LUAN Xingfeng, DENG Li. Development and Benchmark Calculation of Multigroup Monte Carlo Code MCMG[J]. Nuclear Power Engineering, 2007, 28(1): 9-12,17.

Citation:

JIANG Xiaofeng, LUAN Xingfeng, DENG Li. Development and Benchmark Calculation of Multigroup Monte Carlo Code MCMG[J]. Nuclear Power Engineering, 2007, 28(1): 9-12,17.

JIANG Xiaofeng, LUAN Xingfeng, DENG Li. Development and Benchmark Calculation of Multigroup Monte Carlo Code MCMG[J]. Nuclear Power Engineering, 2007, 28(1): 9-12,17.

Citation:

JIANG Xiaofeng, LUAN Xingfeng, DENG Li. Development and Benchmark Calculation of Multigroup Monte Carlo Code MCMG[J]. Nuclear Power Engineering, 2007, 28(1): 9-12,17.

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Development and Benchmark Calculation of Multigroup Monte Carlo Code MCMG

1. Department of Nuclear Science and System Engineering, Shanghai Jiaotong University, 00030, China;
2. Qinshan Nuclear Power Company, Haiyan, Zhejiang, 314300, China;
3. Institute of Applied Physics and Computational Mathematics, Beijing, 100088, China

Received Date: 2005-07-18
Rev Recd Date: 2006-09-15

Available Online: 2025-07-21

Abstract

Abstract

A multigroup Monte Carlo Code MCMG is developed based on the continuous-energy Monte Carlo Code MCNP.The continuous-energy point-cross sections are substituted by the homogenized multi-group cross sections as the function of burnup by the lattice code WIMS,which speedup the computation procedures and supply the capability of burnup simulations for the Monte Carlo Code.Because of the phenomenon that the negative self-scattering cross sections cause the negative probability sample,a nonnegative corrected method is put forward and validated by the benchmark problems.
- Multigroup,
- Monte Carlo,
- Homogenized cross sections,
- MCMG