Generation, Testing, and Validation of a WIMS-D/4 Multigroup Cross-Section Library Based on the JENDL-3.2 Nuclear Data

• Published in: Nuclear technology 2001-03, Vol.133 (3), p.346-354
• Main Authors: Rahman, Mafizur, Takano, Hideki
• Format: Article
• Language: English
• Subjects: Applied sciences; BENCHMARKS; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; Installations for energy generation and conversion: thermal and electrical energy; NUCLEAR DATA COLLECTIONS; NUCLEAR FUELS; PLUTONIUM; SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; THERMAL REACTORS; URANIUM; VALIDATION; ZERO POWER REACTORS
• ISSN: 0029-5450; 1943-7471
• DOI: 10.13182/NT01-A3179

A new 69-group library of multigroup constants for the lattice code WIMS-D/4 has been generated with an improved resonance treatment, processing nuclear data from JENDL-3.2 by NJOY91.108. A parallel ENDF/B-VI based library has also been constructed for intercomparison of results. Benchmark calculations for a number of thermal reactor critical assemblies of both uranium and plutonium fuels have been performed with the code WIMS-D/4.1 with its three different libraries: the original WIMS library (NEA-0329/10) and the new ENDF/B-VI and JENDL-3.2 based libraries. The results calculated with both ENDF and JENDL based libraries show a similar tendency and are found in better agreement with the experimental values. Benchmark parameters are further calculated with the comprehensive lattice code SRAC95. The results from SRAC95 and WIMS-D/4.1 (both using JENDL-3.2 based libraries) agree well with each other. The new library is also verified for its applicability to mixed-oxide cores of varying plutonium contents.