Published 2007 | Version v1
Book Metadata-only

Flux-limited diffusion coefficients in reactor physics applications

Creators

  • 1. Nuclear and Radiological Engineering/Medical Physics Program, George W. Woodruff School of Mechanical Engineering, Georgia Inst. of Technology, Atlanta, GA 30332-0405 (United States)
  • 2. Idaho National Laboratory, Nuclear Programs, Nuclear Science and Engineering Division, Idaho Falls, ID 83415 (United States)

Description

Flux-limited diffusion theory has been successfully applied to problems in radiative transfer and radiation hydrodynamics, but its relevance to reactor physics has not yet been explored. The current investigation compares the performance of a flux-limited diffusion coefficient against the traditionally defined transport cross section. A one-dimensional BWR benchmark problem is examined at both the assembly and full-core level with varying degrees of heterogeneity. (authors)

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park (United States)
ISBN
0-89448-059-6
Imprint Pagination
10 p.

Conference

Title
Joint International Topical Meeting on Mathematics and Computations and Supercomputing in Nuclear Applications
Acronym
M and C + SNA 2007
Dates
15-19 Apr 2007
Place
Monterey, CA (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
42109200
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BENCHMARKS; BWR TYPE REACTORS; CROSS SECTIONS; HYDRODYNAMICS; NEUTRON DIFFUSION EQUATION; ONE-DIMENSIONAL CALCULATIONS; RADIANT HEAT TRANSFER; REACTOR CORES; REACTOR PHYSICS
Descriptors DEC
DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUATIONS; FLUID MECHANICS; HEAT TRANSFER; MECHANICS; PARTIAL DIFFERENTIAL EQUATIONS; PHYSICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
12 refs.