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Reaction Rate Distributions and Ratios in FR0 Assemblies 1, 2 and 3

Abstract

The spatial distribution of different reaction rates and reaction ratios in Assemblies 1, 2 and 3 of the fast reactor FR0 was measured by fission chamber scans and foil activation technique. Assemblies 1 and 2 had cores of undiluted fuel (uranium metal enriched to 20 % U{sup 235}) while the core of Assembly 3 was diluted with about 30 vol. % graphite. All the systems had a thick copper reflector, The experimental results were compared with calculated values obtained from DSN and TDC multigroup spectra and group cross-section sets for the reactions. Good agreement between experiment and calculations is generally obtained in the core region but in the reflector the neutron spectrum is calculated too hard.
Authors:
Publication Date:
Jun 15, 1966
Product Type:
Technical Report
Report Number:
AE-229
Resource Relation:
Other Information: 25 refs., 24 figs., 11 tabs.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FR-0 REACTOR; REACTION KINETICS; SPATIAL DISTRIBUTION; FISSION CHAMBERS; MULTIGROUP THEORY
OSTI ID:
20949508
Research Organizations:
AB Atomenergi, Nykoeping (Sweden)
Country of Origin:
Sweden
Language:
English
Other Identifying Numbers:
TRN: SE0708483
Availability:
Commercial reproduction prohibited; OSTI as DE20949508
Submitting Site:
SWDN
Size:
54 pages
Announcement Date:
Dec 17, 2007

Citation Formats

Andersson, T L. Reaction Rate Distributions and Ratios in FR0 Assemblies 1, 2 and 3. Sweden: N. p., 1966. Web.
Andersson, T L. Reaction Rate Distributions and Ratios in FR0 Assemblies 1, 2 and 3. Sweden.
Andersson, T L. 1966. "Reaction Rate Distributions and Ratios in FR0 Assemblies 1, 2 and 3." Sweden.
@misc{etde_20949508,
title = {Reaction Rate Distributions and Ratios in FR0 Assemblies 1, 2 and 3}
author = {Andersson, T L}
abstractNote = {The spatial distribution of different reaction rates and reaction ratios in Assemblies 1, 2 and 3 of the fast reactor FR0 was measured by fission chamber scans and foil activation technique. Assemblies 1 and 2 had cores of undiluted fuel (uranium metal enriched to 20 % U{sup 235}) while the core of Assembly 3 was diluted with about 30 vol. % graphite. All the systems had a thick copper reflector, The experimental results were compared with calculated values obtained from DSN and TDC multigroup spectra and group cross-section sets for the reactions. Good agreement between experiment and calculations is generally obtained in the core region but in the reflector the neutron spectrum is calculated too hard.}
place = {Sweden}
year = {1966}
month = {Jun}
}