Published September 1999 | Version v1
Book

3D Radiation Transport Benchmarks for Simple Geometries with Void Region

  • 1. Department of Nuclear Engineering, Kyoto University, Yoshida, Sakyoku, Kyoto (Japan)
  • 2. Nuclear Engineering Co., Tosabori 1-3-7, Nishiku, Osaka (Japan)
  • 3. Department of Nuclear Energy System, Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki (Japan)

Description

3D transport benchmark problems for simple geometries with a void region were proposed at OECD/NEA in order to check the accuracy of deterministic 3D transport programs. The exact total fluxes using the analytical method are given for the pure absorber cases, and Monte Carlo values are given for the 50% scattering cases as the reference values. Total fluxes for cases calculated by the 3D transport programs, TORT, PENTRAN, MCCG3D, PARTISN and FNSUNCL3 et.al. are compared in figures. (author)

Part of:
M and C'99 - Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications

Additional details

Publishing Information

Publisher
Senda Editorial S.A.
Imprint Place
Madrid (Spain)
ISBN
84-699-0942-8
Imprint Title
M and C'99 - Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications
Imprint Pagination
2249 p.
Journal Page Range
p. 657-666

Conference

Title
Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications
Acronym
M and C'99
Dates
27-30 Sep 1999
Place
Madrid (Spain)

INIS

Country of Publication
Spain
Country of Input or Organization
France
INIS RN
54116975
Subject category
S97: MATHEMATICAL METHODS AND COMPUTING; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BENCHMARKS; GEOMETRY; MONTE CARLO METHOD; RADIATION TRANSPORT; SCATTERING
Descriptors DEC
CALCULATION METHODS; MATHEMATICS

Optional Information

Notes
15 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses