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Title: ENDF/B-VIII.0 testing with AMPX and SCALE

Conference ·
OSTI ID:22973010
; ;  [1]
  1. Oak Ridge National Laboratory, Oak Ridge, TN (United States)

As the new ENDF/B-VIII.0 data has continued development from its initial beta release into the final release version, it has subsequently undergone processing and testing at Oak Ridge National Laboratory with AMPX and SCALE. Each of the beta releases has been processed with AMPX to create both multigroup (MG) and continuous-energy (CE) libraries. The MG libraries were all processed using the SCALE 252-group structure. These libraries were then used with the VALID suite for benchmarking the new data library's performance against the currently distributed ENDF/B-VII.1 (VII.1)-based SCALE libraries. Here, we compare the MG and CE VALID results for the two current ENDF releases, versions VII.1 and the most recent beta release of ENDF/B-VIII.0 as of this writing (VIII.0.β4). Generally, both the MG and CE VALID aggregate results for VIII.0.β4 compare reasonably well with their VII.1-derived counterparts. As can be expected of any new ENDF release, some of the individual cases have substantially different computed neutron multiplicity (k{sub eff}) values between the two releases, although typically the differences are less than 100 percent-milli (pcm). However, changes to the plutonium cross sections have induced much larger changes in the ratio of the computed k{sub eff} to the experimental value (C/E) for thermal spectrum plutonium solution critical systems. This paper details the comparative performance of the VII.1 and VIII.0.β4 data for the broad range of test cases covered by the VALID suite. A companion paper at this conference provides details of the baseline validation of SCALE 6.2, including the first release of the VII.1 data. (authors)

Research Organization:
American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI ID:
22973010
Resource Relation:
Conference: ANS NCSD 2017: Nuclear Criticality Safety Division topical meeting - Criticality safety, pushing boundaries by modernizing and integrating data, methods, and regulations, Carlsbad, NM (United States), 10-15 Sep 2017; Other Information: Country of input: France; 6 refs.; Available on CD-ROM from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
Country of Publication:
United States
Language:
English