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Author Finck, P. J. ♦ Stenberg, C. G. ♦ Roy, R.
Source United States Department of Energy Office of Scientific and Technical Information
Content type Text
Language English
Subject Keyword NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS ♦ MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS ♦ NUCLEAR WEAPONS DISMANTLEMENT ♦ MIXED OXIDE FUELS ♦ WATER COOLED REACTORS ♦ D CODES ♦ REACTOR KINETICS ♦ VALIDATION ♦ BENCHMARKS
Abstract The US program to dispose of weapons-grade Pu could involve the irradiation of mixed-oxide (MOX) fuel assemblies in commercial light water reactors. This will require licensing acceptance because of the modifications to the core safety characteristics. In particular, core neutronics will be significantly modified, thus making it necessary to validate the standard suites of neutronics codes for that particular application. Validation criteria are still unclear, but it seems reasonable to expect that the same level of accuracy will be expected for MOX as that which has been achieved for UO{sub 2}. Commercial lattice physics codes are invariably claimed to be accurate for MOX analysis but often lack independent confirmation of their performance on a representative experimental database. Argonne National Laboratory (ANL) has started implementing a public domain suite of codes to provide for a capability to perform independent assessments of MOX core analyses. The DRAGON lattice code was chosen, and fine group ENDF/B-VI.04 and JEF-2.2 libraries have been developed. The objective of this work is to validate the DRAGON algorithms with respect to continuous-energy Monte Carlo for a suite of realistic UO{sub 2}-MOX benchmark cases, with the aim of establishing a reference DRAGON scheme with a demonstrated high level of accuracy and no computing resource constraints. Using this scheme as a reference, future work will be devoted to obtaining simpler and less costly schemes that preserve accuracy as much as possible.
ISSN 0003018X
Educational Use Research
Learning Resource Type Article
Publisher Date 1998-12-31
Publisher Place United States
Journal Transactions of the American Nuclear Society
Volume Number 79
Technical Publication No. CONF-981106-


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