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Benchmarking with high-order nodal diffusion methods

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:7122302
;  [1]
  1. Univ. of Michigan, Ann Arbor, MI (United States)
Significant progress in the solution of multidimensional neutron diffusion problems was made in the late 1970s with the introduction of nodal methods. Modern nodal reactor analysis codes provide significant improvements in both accuracy and computing speed over earlier codes based on fine-mesh finite difference methods. In the past, the performance of advanced nodal methods was determined by comparisons with fine-mesh finite difference codes. More recently, the excellent spatial convergence of nodal methods has permitted their use in establishing reference solutions for some important bench-mark problems. The recent development of the self-consistent high-order nodal diffusion method and its subsequent variational formulation has permitted the calculation of reference solutions with one node per assembly mesh size. In this paper, we compare results for four selected benchmark problems to those obtained by high-order response matrix methods and by two well-known state-of-the-art nodal methods (the [open quotes]analytical[close quotes] and [open quotes]nodal expansion[close quotes] methods).
OSTI ID:
7122302
Report Number(s):
CONF-931160--
Conference Information:
Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 69
Country of Publication:
United States
Language:
English

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