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 language | English |
---|---|
Title of host publication | Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021 |
Publisher | American Nuclear Society |
Pages | 808-818 |
Number of pages | 11 |
ISBN (Electronic) | 9781713886310 |
DOIs | |
State | Published - 2021 |
Event | 2021 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021 - Virtual, Online Duration: Oct 3 2021 → Oct 7 2021 |
Publication series
Name | Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021 |
---|
Conference
Conference | 2021 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2021 |
---|---|
City | Virtual, Online |
Period | 10/3/21 → 10/7/21 |
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