应用MCNP程序处理研究堆屏蔽计算深穿透问题的方法研究

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A Methodology Study for Deep Penetration Shielding Calculations of Research Reactors Based on MCNP Code

1. Nuclear Technology Support Center, State Administration of Science, Technology and Industry for National Defense, Beijing, 100080, China;
2. China Institute of Atomic Energy, Beijing, 102413, China

摘要: 采用MCNP程序对某一体化研究堆主屏蔽设计进行验证计算。通过几何分裂、源项模型简化、多群截面和能群截断等方法逐步优化计算模型,计算效率提高了70%,计算结果方差小于10%,与确定论程序计算结果吻合较好。经分析,本文建立的计算方法适用于屏蔽层较厚研究堆的屏蔽计算。
- MCNP程序 /
- 深穿透问题 /
- 屏蔽计算
Abstract: MCNP code was used to execute the verification calculations of the shielding design for a research reactor in this paper.Various techniques including geometry splitting,source term simplification,multi-group cross-section and energy cutoff were introduced to optimize the calculation.The result shows that the output value from MCNP coincides well with that from the deterministic methods.Besides,a significant increasing of the computing efficiency up to 70% and a small variance of the run output lower than 10% were obtained as a result of the application of the aforesaid techniques.Moreover,a conclusion can be drawn from the analysis that the method proposed to deal with the deep penetration problems in this paper is found to be applicable to the shielding calculations of other research reactors with thick shielding.
- MCNP code /
- Deep penetration problems /
- Shielding calculations