Published 1981 | Version v1
Journal article Metadata-only

The constrained finite element approach to coarse-mesh transport computations

Creators

  • 1. Northwestern Univ., Evanston IL (USA). Dept. of Mechanical and Nuclear Engineering

Description

Lattice eigenvalues and average fluxes are computed for an LWR poison cell problem and water gap problem using GLOBAL and FLESHT codes. The constrained finite element problem has also been applied to a number of BWR benchmark problems in six energy groups with upscatter. (author)

Additional details

Publishing Information

Journal Title
Ann. Nucl. Energy
Journal Volume
8
Journal Issue
11-12
Series
Ann. Nucl. Energy.
Journal Page Range
683-687
ISSN
0306-4549

INIS

Country of Publication
United Kingdom
Country of Input or Organization
United Kingdom
INIS RN
13678365
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
BENCHMARKS; BWR TYPE REACTORS; EIGENVALUES; F CODES; G CODES; MULTIGROUP THEORY; NEUTRON TRANSPORT THEORY; POISONING; PWR TYPE REACTORS; REACTOR LATTICES
Descriptors DEC
COMPUTER CODES; REACTORS; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS