Development and Verification of Fast Reactor Multi-Group Cross Section Database Processing Code MGGC1.0

Huang Zifeng; Ma Xubo; Zhu Runze; Li Yaozhou; Zhang Bin

doi:10.13832/j.jnpe.2021.03.0006

Volume 42 Issue 3

Jun. 2021

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Article Navigation > Nuclear Power Engineering > 2021 > 42(3): 6-13

Huang Zifeng, Ma Xubo, Zhu Runze, Li Yaozhou, Zhang Bin. Development and Verification of Fast Reactor Multi-Group Cross Section Database Processing Code MGGC1.0[J]. Nuclear Power Engineering, 2021, 42(3): 6-13. doi: 10.13832/j.jnpe.2021.03.0006

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Huang Zifeng, Ma Xubo, Zhu Runze, Li Yaozhou, Zhang Bin. Development and Verification of Fast Reactor Multi-Group Cross Section Database Processing Code MGGC1.0[J]. Nuclear Power Engineering, 2021, 42(3): 6-13. doi: 10.13832/j.jnpe.2021.03.0006

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Development and Verification of Fast Reactor Multi-Group Cross Section Database Processing Code MGGC1.0

doi: 10.13832/j.jnpe.2021.03.0006

Publish Date: 2021-06-15

Abstract

Abstract

为产生高精度的快堆截面数据，基于一致性N阶的勒让德函数（P_N）近似方法与临界曲率搜索方法，开发了快堆多群截面处理程序MGGC1.0，并进行了多方面基准验证。通过对均匀混合介质的宏观截面验证表明，中子产生截面的相对偏差均小于0.1%，裂变能谱的相对偏差均小于0.25%，总截面由于修正方式不同导致偏差稍大，但绝大多数能群的相对偏差都在0.5%以内。在临界基准实验中与蒙特卡罗程序RMC采用连续点截面的计算结果相比，78%的基准题的偏差都在100 pcm（1 pcm=10^-5）以内，表明MGGC1.0处理截面的精度较好。在此基础上，采用钠冷快堆基准题BN-600进行计算，与基准题参考计算结果相比，输运与扩散2种方法计算所得有效增殖因子的相对偏差分别为0.112%和0.09%，燃料多普勒系数和燃料密度系数的相对偏差分别为1.49%和1.37%，而结构材料钢的多普勒系数与密度系数的相对偏差稍大，分别为18.75%和24.31%，初步分析，偏差较大的原因与窄共振近似的处理方法有关。对于区域的功率分布，基于局部能量沉积模型计算得出的区域功率分布分数与基准参考解的偏差在0.3%之内，符合较好。
- Fastreactor,
- Multi-group cross section,
- MGGC1.0,
- Benchmarkverification,
- BN-600

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