Published July 1999 | Version v1
Journal article Metadata-only

Benchmarking a diffusion code for a cylindrical-core reactor

Creators

  • 1. Oregon Graduate Institute of Science and Technology, Portland, OR (United States)
  • 2. Technion-Israel Institute of Technology, Haifa (Israel)

Description

The distorted-buckling method, proposed by us previously, allows the benchmarking of a diffusion code by comparing it with an analytic model in either 2 or 3 dimensions. Here, the method is applied to the case of a cylindrical TRIGA-type reactor to compare the fluxes predicted by an analytic model of the core and reflector, to those predicted by the code CITATION. The match is everywhere excellent

Additional details

Identifiers

PII
S0306454998001017;

Publishing Information

Journal Title
Annals of Nuclear Energy (Oxford)
Journal Volume
26
Journal Issue
11
Journal Page Range
p. 977-982
ISSN
0306-4549
CODEN
ANENDJ

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
33030041
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ANALYTICAL SOLUTION; BENCHMARKS; BUCKLING; C CODES; COMPARATIVE EVALUATIONS; NEUTRON DIFFUSION EQUATION; NEUTRON REFLECTORS; REACTOR CORES; TRIGA TYPE REACTORS
Descriptors DEC
COMPUTER CODES; DIFFERENTIAL EQUATIONS; ENRICHED URANIUM REACTORS; EQUATIONS; EVALUATION; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Copyright
Copyright (c) 1999 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.