SCALE MG Cross Section Processing for High Void BWR Using the AMPX 1,597-group Library

Technical Report · Fri Sep 28 04:00:00 EDT 2018

DOI:https://doi.org/10.2172/3002111· OSTI ID:3002111

Jeon, Byoung-kyu ^[1]; Yang, Won Sik ^[1]; Kim, Kang Seog ^[2]

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1. Univ. of Michigan, Ann Arbor, MI (United States)
2. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

The CASL VERA neutronic simulator MPACT has been developed by Oak Ridge National Laboratory (ORNL) and University of Michigan for the pressurized water reactor applications. The MPACT capability is being extended for the boiling water reactor (BWR) analysis. Recent investigation showed that the MPACT multigroup (MG) library has limitations for high void BWR fuels because of the very coarse group structure. Since the MPACT MG library is generated with the AMPX/SCALE code package developed at ORNL, enhancement of the AMPX/SCALE code package and its MG library must be preceded to improve the accuracy of the MPACT MG library. Therefore, a new 1597-group structure was developed and an AMPX 1597-group library was generated. This ultra-fine group (UFG) library resulted in significant improvements in accuracy for fast spectrum systems compared to the AMPX 252-group results. However, the use of the AMPX 1597-group library requires significantly increased burden on memory and computing time.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 3002111
• Report Number(s): CASL-U--2018-1674-000
• Country of Publication: United States
• Language: English

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