Validation and Testing of ENDF/B-VII Decay Data

Gauld, I. C.; Pigni, M. T.; Ilas, G.

doi:10.1016/j.nds.2014.06.134

Title: Validation and Testing of ENDF/B-VII Decay Data

Journal Article · Tue Jul 22 00:00:00 EDT 2014 · Nuclear Data Sheets

DOI:https://doi.org/10.1016/j.nds.2014.06.134· OSTI ID:1148846

Gauld, I. C. ^[1]; Pigni, M. T. ^[1]; Ilas, G. ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

The nuclear decay library developed for the ORIGEN code was upgraded from ENDF/B-VI.8 to -VII.0 and released in the SCALE nuclear modeling and simulation code system in 2011. Experience with the ENDF/B-VII.0 library identified serious errors and performance issues in the evaluated decay sublibrary. Initially, errors were identified in the decay scheme for the 238U series, leading to large discrepancies in the gamma emission rate for uranium. Further testing of the fission product decay data revealed significant performance issues with ENDF/B-VII.0 relative to the previous release of ENDF/B-VI. To address the performance issues, the decay data library in SCALE was upgraded to ENDF/B-VII.1 and released as an update for users in 2013. This paper describes the practical impact of the ENDF/B-VII.0 decay data performance issues on common code applications, and the validation and testing performed on the updated ORIGEN libraries developed from the ENDF/B-VII.1 sublibrary.

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Research Organization:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Science (SC)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1148846

Journal Information:: Nuclear Data Sheets, Vol. 120; Conference: International Conference on Nuclear Data for Science and Technology (ND2013), New York, NY (United States), 4-8 March 2013; ISSN 0090-3752

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 4 works

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References (8)

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SCALE analysis of CLAB decay heat measurements for LWR spent fuel assemblies Ilas, Germina; Gauld, Ian C. Annals of Nuclear Energy, Vol. 35, Issue 1 https://doi.org/10.1016/j.anucene.2007.05.017	journal	January 2008
ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data Chadwick, M. B.; Herman, M.; Obložinský, P. Nuclear Data Sheets, Vol. 112, Issue 12 https://doi.org/10.1016/j.nds.2011.11.002	journal	December 2011
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Validation of new depletion capabilities and ENDF/B-VII data libraries in SCALE Ilas, Germina; Gauld, Ian C.; Radulescu, Georgeta Annals of Nuclear Energy, Vol. 46 https://doi.org/10.1016/j.anucene.2012.03.012	journal	August 2012
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