Published August 1986 | Version v1
Report Metadata-only

Calculation of 3-D flux distributions in CANDU reactors using lattice properties dependent on several local parameters

Creators

  • 1. Atomic Energy of Canada Ltd., Mississauga, Ontario

Description

A refinement is proposed to the current method of evaluating lattice properties for use in calculations of CANDU flux distributions. This refinement, labelled 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

Imprint Title
Proceedings of the topical meeting on reactor physics and safety: Sessions 11-16. Volume 2
Journal Page Range
p. 884-895.
Report number
NUREG/CP--0080-Vol.2

Conference

Title
Advances in reactor physics and safety meeting.
Dates
17-19 Sep 1986.
Place
Saratoga Springs, NY (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
18028652
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CANDU TYPE REACTORS; FUEL ELEMENTS; FUEL MANAGEMENT; IRRADIATION; NEUTRON FLUX; POWER DENSITY; REACTOR CHANNELS; REACTOR CORES; REACTOR PHYSICS; SPECIFICATIONS; TEMPERATURE DEPENDENCE
Descriptors DEC
HEAVY WATER MODERATED REACTORS; MANAGEMENT; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; PRESSURE TUBE REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS