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Development of the evaluation methods in reactor safety analyses and core characteristics

Abstract

In order to support the safety reviews by NRA on reactor safety design including the phenomena with multiple failures, the computer codes are developed and the safety evaluations with analyses are performed in the areas of thermal hydraulics and core characteristics evaluation. In the code preparation of safety analyses, the TRACE and RELAP5 code were prepared to conduct the safety analyses of LOCA and beyond design basis accidents with multiple failures. In the core physics code preparation, the functions of sensitivity and uncertainty analysis were incorporated in the lattice physics code CASMO-4. The verification of improved CASMO-4 /SIMULATE-3 was continued by using core physics data. (author)
Authors:
"NONE"
Publication Date:
Aug 15, 2013
Product Type:
Technical Report
Report Number:
JNES-RE-2013-0001
Resource Relation:
Other Information: 4 refs., 15 figs., 3 tabs.; Related Information: In: Annual safety research report, JFY 2012| Japan Nuclear Energy Safety Organization, Tokyo (Japan)| 708 p.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ATWS; BENCHMARKS; EVALUATION; LOSS OF COOLANT; REACTOR CORES; SAFETY ANALYSIS; SAFETY MARGINS; SENSITIVITY ANALYSIS; THERMAL HYDRAULICS; VOID FRACTION
OSTI ID:
22325940
Research Organizations:
Japan Nuclear Energy Safety Organization, Nuclear Energy System Safety Department, Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
TRN: JP1501462032157
Availability:
Available from the Internet at URL http://www.nsr.go.jp/archive/jnes/content/000125907.pdf
Submitting Site:
INIS
Size:
page(s) 7-15
Announcement Date:
Apr 14, 2015

Citation Formats

Development of the evaluation methods in reactor safety analyses and core characteristics. Japan: N. p., 2013. Web.
Development of the evaluation methods in reactor safety analyses and core characteristics. Japan.
2013. "Development of the evaluation methods in reactor safety analyses and core characteristics." Japan.
@misc{etde_22325940,
title = {Development of the evaluation methods in reactor safety analyses and core characteristics}
abstractNote = {In order to support the safety reviews by NRA on reactor safety design including the phenomena with multiple failures, the computer codes are developed and the safety evaluations with analyses are performed in the areas of thermal hydraulics and core characteristics evaluation. In the code preparation of safety analyses, the TRACE and RELAP5 code were prepared to conduct the safety analyses of LOCA and beyond design basis accidents with multiple failures. In the core physics code preparation, the functions of sensitivity and uncertainty analysis were incorporated in the lattice physics code CASMO-4. The verification of improved CASMO-4 /SIMULATE-3 was continued by using core physics data. (author)}
place = {Japan}
year = {2013}
month = {Aug}
}