You need JavaScript to view this

Validation study of core analysis methods for full MOX BWR

Abstract

JNES has been developing a technical database used in reviewing validation of core analysis methods of LWRs in the coming occasions: (1) confirming the core safety parameters of the initial core (one-third MOX core) through a full MOX core in Oma Nuclear Power Plant, which is under the construction, (2) licensing high-burnup MOX cores in the future and (3) reviewing topical reports on core analysis codes for safety design and evaluation. Based on the technical database, JNES will issue a guide of reviewing the core analysis methods used for safety design and evaluation of LWRs. The database will be also used for validation and improving of core analysis codes developed by JNES. JNES has progressed with the projects: (1) improving a Doppler reactivity analysis model in a Monte Carlo calculation code MVP, (2) sensitivity study of nuclear cross section date on reactivity calculation of experimental cores composed of UO{sub 2} and MOX fuel rods, (3) analysis of isotopic composition data for UO{sub 2} and MOX fuels and (4) the guide of reviewing the core analysis codes and others. (author)
Authors:
"NONE"
Publication Date:
Aug 15, 2013
Product Type:
Technical Report
Report Number:
JNES-RE-2013-0001
Resource Relation:
Other Information: 11 refs., 5 figs.; 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; BURNUP EXTENSION; BWR TYPE REACTORS; DOPPLER COEFFICIENT; FISSION PRODUCTS; MIXED OXIDE FUELS; NUMERICAL ANALYSIS; PLUTONIUM; REACTOR CORES; SENSITIVITY ANALYSIS; URANIUM DIOXIDE; VALIDATION
OSTI ID:
22325941
Research Organizations:
Japan Nuclear Energy Safety Organization, Nuclear Energy System Safety Department, Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
TRN: JP1501463032158
Availability:
Available from the Internet at URL http://www.nsr.go.jp/archive/jnes/content/000125907.pdf
Submitting Site:
INIS
Size:
page(s) 17-24
Announcement Date:
Apr 14, 2015

Citation Formats

Validation study of core analysis methods for full MOX BWR. Japan: N. p., 2013. Web.
Validation study of core analysis methods for full MOX BWR. Japan.
2013. "Validation study of core analysis methods for full MOX BWR." Japan.
@misc{etde_22325941,
title = {Validation study of core analysis methods for full MOX BWR}
abstractNote = {JNES has been developing a technical database used in reviewing validation of core analysis methods of LWRs in the coming occasions: (1) confirming the core safety parameters of the initial core (one-third MOX core) through a full MOX core in Oma Nuclear Power Plant, which is under the construction, (2) licensing high-burnup MOX cores in the future and (3) reviewing topical reports on core analysis codes for safety design and evaluation. Based on the technical database, JNES will issue a guide of reviewing the core analysis methods used for safety design and evaluation of LWRs. The database will be also used for validation and improving of core analysis codes developed by JNES. JNES has progressed with the projects: (1) improving a Doppler reactivity analysis model in a Monte Carlo calculation code MVP, (2) sensitivity study of nuclear cross section date on reactivity calculation of experimental cores composed of UO{sub 2} and MOX fuel rods, (3) analysis of isotopic composition data for UO{sub 2} and MOX fuels and (4) the guide of reviewing the core analysis codes and others. (author)}
place = {Japan}
year = {2013}
month = {Aug}
}