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Title: Validation of the SCALE broad structure 44-group ENDF/B-V cross-section library for use in criticality safety analyses

Technical Report ·
DOI:https://doi.org/10.2172/10188396· OSTI ID:10188396
;  [1]
  1. Oak Ridge National Lab., TN (United States)

This report documents the validation of the recently developed 44-group ENDF/B-V based cross-section library (44GROUPNDF5). This cross-section set has been developed for use in the SCALE code system in the analysis of fresh and spent fuel and radioactive waste systems. Collapsed from a 238-group fine-structure cross-section library (238GROUPNDF5), this broad-group library contains approximately 300 nuclides from the ENDF/B-V data files. Additionally, ENDF/B-VI oxygen data have been substituted for ENDF/B-V oxygen, because of discrepancies in ENDF/B-V data. The 44 GROUPNDF5 library was tested against its parent library using a set of 33 benchmark problems in order to demonstrate that the collapsed set was an acceptable representation of 238GROUPNDF5. Results show that the broad 44-group structure is an acceptable representation of its parent 238-group library for thermal as well as hard fast spectrum systems. Accurate broad-group analyses of intermediate spectrum systems will require either a more detailed group structure in this energy range or a more appropriate collapsing spectrum. Further, validation calculations indicate that the 44-group library is an accurate tool in the prediction of criticality for arrays of light-water-reactor-type fuel assemblies, as would be encountered in fresh or spent fuel transportation or storage environments. However, a bias caused by inadequate representation of plutonium cross sections was identified. Further, a possible bias exists with respect to uranium enrichment; however, experiments referenced in this report provide an inadequate sampling of uranium enrichments. Additional work will be required to quantify any bias that may be present.

Research Organization:
US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Regulatory Applications; Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
Nuclear Regulatory Commission, Washington, DC (United States)
OSTI ID:
10188396
Report Number(s):
NUREG/CR-6102; ORNL/TM-12460; ON: TI95001054; TRN: 94:021059
Resource Relation:
Other Information: PBD: Sep 1994
Country of Publication:
United States
Language:
English