Published January 1985 | Version v1
Report

Australian benchmark calculations. App. F-3

  • 1. Australian Atomic Energy Commission Research Establishment, Lucas Heights

Description

Calculations of the methodical benchmark problem have been undertaken using methods developed at the AAEC and incorporated in the AUS modular code scheme (Robinson 1975a). These calculations for HEU and LEU fuel consist of cell burnup for the DIDO-type fuel element, and diffusion theory applied to an X-Y representation of reactor core. Brief descriptions of the computer codes used and their application to this problem are given, together with results for HEU and LEU fuel element cell burn-up and 2-dimensional diffusion theory (X-Y) reactor core calculations

Part of:
Research reactor core conversion from the use of highly enriched uranium to the use of low enriched uranium fuels. Guidebook addendum: Heavy water moderated reactors

Additional details

Publishing Information

Imprint Title
Research reactor core conversion from the use of highly enriched uranium to the use of low enriched uranium fuels. Guidebook addendum: Heavy water moderated reactors
Imprint Pagination
253 p.
Journal Page Range
p. 215-229.
Report number
IAEA-TECDOC--324

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
16058499
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Numerical Data
Descriptors DEI
BENCHMARKS; COMPUTER CALCULATIONS; FUEL ELEMENTS; HEAVY WATER MODERATED REACTORS; HIGHLY ENRICHED URANIUM; MODERATELY ENRICHED URANIUM; NEUTRON FLUX; REACTIVITY COEFFICIENTS; REACTOR CORES; SPECIFICATIONS; THEORETICAL DATA; TWO-DIMENSIONAL CALCULATIONS
Descriptors DEC
ACTINIDES; DATA; ELEMENTS; ENRICHED URANIUM; INFORMATION; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; NUMERICAL DATA; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; URANIUM

Optional Information