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CMFD加速在特征线法输运计算中的应用 被引量：6

Application of Coarse-Mesh Finite Difference Acceleration in Transportation Calculation by Method of Characteristics
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摘要 为解决特征线法求解复杂几何条件下中子输运问题收敛速度慢的问题,将粗网扩散计算中的粗网有限差分(CMFD:Coarse-Mesh Finite Difference)加速方法运用于中子输运计算中。采用粗网有限差分加速方法对C5G7MOX基准问题以及自定义的69群检验算例的计算表明,CMFD加速是一种十分高效的方法,可显著地提高特征线法求解中子输运问题的收敛速度,且问题规模越大,加速效果越明显。 In order to address the low convergence issue of the method of characteristics, the coarse-mesh finite difference （CMFD） formulation, which is a widely recognized acceleration technique for coarse mesh diffusion calculation, is studied to speedup the MOC transport calculation. Numerical tests on C5G7 MOX benchmark problem and a 69 group test problem defined based on C5 demonstrate that CMFD acceleration is quite efficient in reducing the number of MOC iterations and the computing time. It also shows that the larger scale of the problem, the better effect of the CMFD acceleration.
作者 汤春桃 张少泓
机构地区 上海交通大学核科学与工程学院
出处 《核动力工程》 EI CAS CSCD 北大核心 2009年第5期8-12,共5页 Nuclear Power Engineering
基金 国家自然科学基金资助项目(10605016)
关键词 粗网有限差分 加速方法 特征线法(MOC) Coarse-mesh finite difference, Acceleration method, Method of characteristics.
分类号 TL329.2 [核科学技术—核技术及应用]
  • 相关文献

参考文献6

  • 1汤春桃,张少泓.以栅元为模块进行特征线跟踪的中子输运方程解法[J].核动力工程,2009,30(4):32-36. 被引量：4
  • 2Smith K S. Nodal Method Strategy Reduction by Nonlinear Iteration[J]. Transactions of the American Nuclear Society, 1983, 44: 265.
  • 3Zhaopeng Zhong, Thomas J Downar, Yunlin Xu, et al. Implementation of Two-Level Coarse-Mesh Finite Difference Acceleration in an Arbitrary Geometry, Two- Dimensional Discrete Ordinates Transport Method[J]. Nuclear Science and Engineering, 2008, 158: 289-198.
  • 4Han Gyu Joo, Jin Young-Cho, Ha Yong Kim, et al. Dynamic Implementation of the Equivalence Theory in the Heterogeneous Whole Core Transport Calculation[C]. PHYSOR-2002, Seoul, Korea, October 7-10, 2002.
  • 5Lewis E E, Michael A Smith and Byung-Chan Na. Special Issue: OECD/NEA Benchmark on MOX-fuelled Core Transport Calculations without Spatial Homogenization [J]. Progress in Nuclear Energy, 2004, 45(2 - 4): 105 - 265.
  • 6Deng Li, Xie Zhongsheng, Zhang Jianming. A 3-D Multi-Group P3 Monte Carlo Code and Its Benchmarks [J]. Journal of Nuclear Science and Technology, 2000, 37(7): 608 - 614.

二级参考文献5

  • 1Tatjana Jevremovic, Takuya Ito, Yuzo Inaba. ANEM- ONA: Multiassembly Neutron Transport Modeling[J]. Annals of Nuclear Energy, 2002, 29:2105 - 2125.
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共引文献3

同被引文献21

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引证文献6

二级引证文献4

核动力工程
2009年 第5期

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