Published January 1990 | Version v1
Journal article Metadata-only

Thermal disadvantage factor

Creators

  • 1. Missouri Univ., Columbia, MO (USA). Dept. of Nuclear Engineering

Description

A method is described where reactor cell flux and the disadvantage factor are calculated by using diffusion theory in the moderator and integral transport in the fuel. The method is efficient (noniterative) and provides results that agree well with Monte Carlo, P5 and ABH results

Additional details

Additional titles

Subtitle (English)
An efficient calculation

Publishing Information

Journal Title
Nuclear Science and Engineering
Journal Volume
104
Journal Issue
1
Series
Nucl. Sci. Eng.
Journal Page Range
34-39
ISSN
0029-5639
CODEN
NSENA

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
21087639
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Descriptors DEI
ALGORITHMS; NEUTRON FLUX; NEUTRON TRANSPORT THEORY; REACTOR KINETICS EQUATIONS
Descriptors DEC
EQUATIONS; RADIATION FLUX; TRANSPORT THEORY