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Neutronic analysis on JRR-4 core by the use of low enriched uranium silicide fuels with several uranium densities

Technical Report:

Abstract

The reduced enrichment program for JRR-4 has been going on in the Department of Research Reactor. Neutronic calculations using SRAC code system have been carried out in order to evaluate the neutronic characteristics of the core with low enriched uranium silicide fuel. In the calculations, changes of some neutronic characteristics were evaluated by changing the uranium density in the fuel meat. Analysis on the core with high enriched fuel was also performed to compare its characteristics with the silicide core. From these results obtained, it has been found that the uranium density of about 3.8 gU/cm{sup 3} (for the inner plates) is adequate for JRR-4. Some calculations have been done to evaluate the effect of the change of neutron cross section libraries on the calculated results by using the continuous energy Monte Carlo code VIM. Results by VIM code were compared and showed very good agreements with ones by SRAC code. (author).
Authors:
Nakano, Yoshihiro [1] 
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Publication Date:
Jul 01, 1992
Product Type:
Technical Report
Report Number:
JAERI-M-92-103
Reference Number:
SCA: 220600; PA: JPN-92:011244; SN: 93000918649
Resource Relation:
Other Information: PBD: Jul 1992
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; REACTOR CORES; JRR-4 REACTOR; MODERATELY ENRICHED URANIUM; DENSITY; URANIUM SILICIDES; NEUTRONS; CROSS SECTIONS; MONTE CARLO METHOD; REACTOR LATTICES; FUEL PLATES; SPATIAL DISTRIBUTION; BURNUP; CONTROL ROD WORTHS; 220600; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS
OSTI ID:
10111315
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE93753323; TRN: JP9211244
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
73 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Nakano, Yoshihiro. Neutronic analysis on JRR-4 core by the use of low enriched uranium silicide fuels with several uranium densities. Japan: N. p., 1992. Web.
Nakano, Yoshihiro. Neutronic analysis on JRR-4 core by the use of low enriched uranium silicide fuels with several uranium densities. Japan.
Nakano, Yoshihiro. 1992. "Neutronic analysis on JRR-4 core by the use of low enriched uranium silicide fuels with several uranium densities." Japan.
@misc{etde_10111315,
title = {Neutronic analysis on JRR-4 core by the use of low enriched uranium silicide fuels with several uranium densities}
author = {Nakano, Yoshihiro}
abstractNote = {The reduced enrichment program for JRR-4 has been going on in the Department of Research Reactor. Neutronic calculations using SRAC code system have been carried out in order to evaluate the neutronic characteristics of the core with low enriched uranium silicide fuel. In the calculations, changes of some neutronic characteristics were evaluated by changing the uranium density in the fuel meat. Analysis on the core with high enriched fuel was also performed to compare its characteristics with the silicide core. From these results obtained, it has been found that the uranium density of about 3.8 gU/cm{sup 3} (for the inner plates) is adequate for JRR-4. Some calculations have been done to evaluate the effect of the change of neutron cross section libraries on the calculated results by using the continuous energy Monte Carlo code VIM. Results by VIM code were compared and showed very good agreements with ones by SRAC code. (author).}
place = {Japan}
year = {1992}
month = {Jul}
}