Published February 1988 | Version v1
Journal article Metadata-only

Calculation of three-dimensional flux distributions in CANDU reactors using lattice properties dependent on several local parameters

Creators

  • 1. Atomic Energy of Canada Ltd., CANDU Operations, Sheridan Park Research Community, Mississauga, Ontario (Canada)

Description

A refinement is proposed to the current method of evaluating lattice properties for use in calculations of Canada deuterium uranium flux distributions. This refinement, labeled the local-parameter calculation, takes into account locally appropriate values of coolant density, fuel temperature, and flux/power level where core average values were previously used. The local-parameter calculation has been implemented and tested. Results are compared to those of previous calculations and of independent methods based on in-core measurements

Additional details

Publishing Information

Journal Title
Nucl. Sci. Eng.
Journal Volume
98
Journal Issue
2
Series
Nucl. Sci. Eng.
Journal Page Range
139-148
ISSN
0029-5639
CODEN
NSENA

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
19089513
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ALGORITHMS; ATOMIC ENERGY OF CANADA LTD; CANDU TYPE REACTORS; IN CORE INSTRUMENTS; POWER DENSITY; POWER DISTRIBUTION; RADIATION FLUX; REACTOR COMPONENTS; REACTOR CORES; REACTOR LATTICE PARAMETERS; REACTOR LATTICES; REACTOR PHYSICS; SPECIFICATIONS
Descriptors DEC
CANADIAN ORGANIZATIONS; DISTRIBUTION; HEAVY WATER MODERATED REACTORS; NATIONAL ORGANIZATIONS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SPATIAL DISTRIBUTION; THERMAL REACTORS