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Improvements of the CMFD acceleration capability of OpenMOC

  • Wu, Wenbin (Department of Nuclear Science and Engineering, Massachusetts Institute of Technology) ;
  • Giudicelli, Guillaume (Department of Nuclear Science and Engineering, Massachusetts Institute of Technology) ;
  • Smith, Kord (Department of Nuclear Science and Engineering, Massachusetts Institute of Technology) ;
  • Forget, Benoit (Department of Nuclear Science and Engineering, Massachusetts Institute of Technology) ;
  • Yao, Dong (Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China) ;
  • Yu, Yingrui (Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China) ;
  • Luo, Qi (Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China)
  • Received : 2019.11.28
  • Accepted : 2020.04.01
  • Published : 2020.10.25

Abstract

Due to its computational efficiency and geometrical flexibility, the Method of Characteristics (MOC) has been widely used for light water reactor lattice physics analysis. Usually acceleration methods are necessary for MOC to achieve acceptable convergence on practical reactor physics problems. Among them, Coarse Mesh Finite Difference (CMFD) is very popular and can drastically reduce the number of transport iterations. In OpenMOC, CMFD acceleration was implemented but had the limitation of supporting only a uniform CMFD mesh, which would often lead to splitting MOC source regions, thus creating an unnecessary increase in computation and memory use. In this study, CMFD acceleration with a non-uniform Cartesian mesh is implemented into OpenMOC. We also propose a quadratic fit based CMFD prolongation method in the axial direction to further improve the acceleration when multiple MOC source regions are contained in one CMFD coarse mesh. Numerical results are presented to demonstrate the improvement of the CMFD acceleration capability in OpenMOC in terms of both efficiency and stability.

Keywords

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  1. Method of Characteristics for 3D, Full-Core Neutron Transport on Unstructured Mesh vol.207, pp.7, 2020, https://doi.org/10.1080/00295450.2021.1871995