Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)

Korean Nuclear Society (한국원자력학회)
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An Efficient Multigrid Algorithm for the Reactor Eigenvalue Problems

  • Cho, Nam-Zin (Korea Advanced Institute of Science and Technology Department of Nuclear Engineering) ;
  • Lee, Kang-Hyun (Korea Advanced Institute of Science and Technology Department of Nuclear Engineering) ;
  • Kim, Yong-Hee (Korea Electric Power Research Institute Reactor Core and Fuel Analysis Group)
  • Published : 1997.05.01
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Abstract

In this paper, a new multigrid method is developed to solve the reactor eigenvalue problems. The new algorithm can be used in any matrix equation concerned with the eigenvalue problem. The finite difference neutron diffusion problem is considered demonstration of the performance of the new multigrid algorithm. The numerical results show that the new multigrid algorithm works well and requires much shorter (7~10 times) computing time compaired to the production code VENTURE.

Keywords