Published 1983 | Version v1
Journal article Metadata-only

Power-reactor performance evaluation using nodal/modal analysis

Creators

Description

An analytical procedure for calculating the 3-D power distribution in LWRs based on two-group coarse-mesh nodal analysis is described. The use of source-sink analysis of the fast-neutron source distribution yields a very efficient eigenvalue equation. Neutron coupling between nodes is evaluated using a modal analysis of the neutron-source shape within each node based on the multiplication and transport properties of the source node and its immediate neighbors. Both the core and fuel-assembly geometry and the neutronic characteristics of LWRs are particularly well suited to this type of analysis. (author)

Additional details

Publishing Information

Journal Title
Ann. Nucl. Energy
Journal Volume
10
Journal Issue
8
Series
Ann. Nucl. Energy.
Journal Page Range
395-403
ISSN
0306-4549

INIS

Country of Publication
United Kingdom
Country of Input or Organization
United Kingdom
INIS RN
15014096
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BENCHMARKS; BWR TYPE REACTORS; COUPLING; MATHEMATICAL MODELS; NEUTRON FLUX; PERFORMANCE; POWER DISTRIBUTION; PWR TYPE REACTORS; REACTIVITY; THREE-DIMENSIONAL CALCULATIONS
Descriptors DEC
DISTRIBUTION; RADIATION FLUX; REACTORS; SPATIAL DISTRIBUTION; WATER COOLED REACTORS; WATER MODERATED REACTORS