ON THE CREATION OF THE NEW ENDF/B-VIII.0 COVARIANCE LIBRARY FOR SCALE APPLICATIONS WITH AMPX

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Abstract

A new revision of the ENDF/B nuclear data library, ENDF/B-VIII.0, was released in 2018. The AMPX code system was used to generate a new covariance library based on this release for the application with the SCALE code system. The presence of invalid matrix elements required the implementation of a procedure for correcting correlation matrices in AMPX. The new covariance library was used in uncertainty analyses of a light water reactor and a sodium-cooled fast reactor fuel pin cell to assess: (1) the impact of the correlation matrix corrections and (2) the impact of the changes in nuclear data from ENDF/B-VII.1 to ENDF/B-VIII.0. The correction of the correlation matrices in case of invalid matrix elements led to up to a ~10% decrease in uncertainties for several investigated output quantities. Updates of relevant cross section uncertainties in ENDF/B-VIII.0 data led to significant changes in various output quantities, ranging from ~88% decreased uncertainties to up to ~150% increased uncertainties. In particular, updates in 235/238U n,γ, 235/238U χ, 238U inelastic scattering, 239Pu fission, and 56Fe and 16O elastic scattering were found to be relevant.

Original languageEnglish
Title of host publicationProceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021
PublisherAmerican Nuclear Society
Pages808-818
Number of pages11
ISBN (Electronic)9781713886310
DOIs
StatePublished - 2021
Event2021 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021 - Virtual, Online
Duration: Oct 3 2021Oct 7 2021

Publication series

NameProceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021

Conference

Conference2021 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021
CityVirtual, Online
Period10/3/2110/7/21

Funding

This work was sponsored by the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, and the Nuclear Criticality Safety Program, which is funded and managed by the National Nuclear Security Administration for the US Department of Energy. Marco Pigni’ s work on updating the 235U ENDF file for the ENDF/B-VIII.0 nuclear data library is highly appreciated. *This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan).

Keywords

  • AMPX
  • ENDF/B-VIII.0
  • SCALE
  • covariance data
  • uncertainty analysis

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