CASMO-4/SIMULATE-3 benchmarking against high plutonium content pressurized water reactor mixed-oxide fuel critical experiment
Journal Article
·
· Nuclear Science and Engineering
OSTI ID:109980
- Nuclear Engineering, Ltd., Osaka (Japan)
- Kansai Electric Power Co., Osaka (Japan)
A benchmark study is presented of new methodologies of the Studsvik CASMO-4/SIMULATE-3 advanced nuclear design code system against a pressurized water reactor (PWR)-type mixed-oxide (MOX) fuel critical experiment with high plutonium content. Both CASMO-4 two-dimensional transport core calculations and SIMULATE-3 nodal core calculations that use the pin power reconstruction model are performed for the experimental geometries. All the assembly two-group constants for SIMULATE-3, including those for MOX assemblies, are generated by CASMO-4 single-assembly calculations. The CASMO-4 improved transmission probability method and the SIMULATE-3 improved nodal and spectral interaction models are verified to be effective for accurate prediction of the pin power distribution inside high plutonium content PWR MOX assemblies and UO{sub 2} assemblies that are adjacent to the MOX assemblies.
- OSTI ID:
- 109980
- Journal Information:
- Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Journal Issue: 1 Vol. 121; ISSN NSENAO; ISSN 0029-5639
- Country of Publication:
- United States
- Language:
- English
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