Published 1993 | Version v1
Journal article

Benchmarking with high-order nodal diffusion methods

  • 1. Univ. of Michigan, Ann Arbor, MI (United States)

Description

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 analyticalclose quotes and open-quotes nodal expansionclose quotes methods)

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
69
Journal Page Range
p. 212-214.
ISSN
0003-018X
CODEN
TANSAO

Conference

Title
American Nuclear Society (ANS) winter meeting.
Dates
14-18 Nov 1993.
Place
San Francisco, CA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
26027528
Subject category
S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BENCHMARKS; CALCULATION METHODS; NEUTRON DIFFUSION EQUATION; REACTOR KINETICS; SOLUTIONS
Descriptors DEC
DISPERSIONS; HOMOGENEOUS MIXTURES; KINETICS; MIXTURES

Optional Information

Secondary number(s)
CONF-931160--.