Validation of SCALE-4 for a Reference Problem Set

Technical Report · Sun Jun 30 20:00:00 EDT 1991

DOI:https://doi.org/10.2172/5654760· OSTI ID:5654760

Bowman, Stephen M. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

This report presents the results of criticality calculations performed to validate the recently released SCALE-4 modular code system for light water reactor (LWR) fuel for a proposed reference problem set of critical experiments which model various conditions typical of transportation and storage casks. In order to validate SCALE-4, the CSAS4 control module was used to calculate the effective neutron multiplication factor (k_eff) via the BONAMI, NITAWL-2, and KENO V.a codes. Calculations were performed with both SCALE-4 and SCALE-3. The cross-section libraries used were the 27-group ENDF/B-IV library (27GROUPNDF4) and the 27-group ENDF/B-4 burnup library (27BURNUPLIB). The 27BURNUPLIB library is an extension of the 27GROUPNDF4 library to include fission product nuclides which are necessary for depleted fuel analysis. The added fission product cross sections were obtained from ENDF/B-V data.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5654760
• Report Number(s): ORNL/M--1332; ON: DE91016050
• Country of Publication: United States
• Language: English

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