View in EDS

Unresolved resonance parameter evaluation and uncertainty quantification of [formula omitted]181Ta reactions.

Saved in:
Bibliographic Details
Title: Unresolved resonance parameter evaluation and uncertainty quantification of [formula omitted]181Ta reactions.
Authors: Brown, Jesse M.1 (AUTHOR) brownjm@ornl.gov, Barry, Devin P.2 (AUTHOR), Lewis, Amanda2 (AUTHOR), Trumbull, Timothy H.2 (AUTHOR), Pigni, Marco T.1 (AUTHOR), Greene, Travis1 (AUTHOR), Block, Robert C.3 (AUTHOR), Golas, Alec3 (AUTHOR), Danon, Yaron3 (AUTHOR)
Source: Annals of Nuclear Energy. Mar2025, Vol. 212, pN.PAG-N.PAG. 1p.
Subjects: Data libraries, Resonance effect, Neutron temperature, Data release, Criticality (Nuclear engineering)
Abstract: Nuclear technology applications, including reactor modeling, accelerator design, and isotope production, strongly depend on evaluated nuclear data libraries and their uncertainty information for the assessment of predictive accuracy of calculated quantities. Major nuclear data libraries such as JENDL-5, JEFF-3.3, and ENDF/B-VIII.0 lack uncertainty information for n + 181Ta reactions. In addition to the lack of evaluated uncertainty information even in major nuclear data library releases, the most current US ENDF/B-VIII.0 evaluation of the unresolved resonance region (URR) does not extend to high enough energies to appropriately account for resonance self-shielding effects. This work addresses these shortcomings through a new evaluation of the URR, performed with the SAMMY evaluation tool, which extends the evaluation of the URR to encompass neutron energies of 2.5 keV to 100 keV. This study reports evaluated covariances and includes newly measured data in the evaluation analysis that were unavailable to previous evaluators. The new evaluation was designed to be closely coupled to the resolved resonance region evaluation to improve consistency across multiple evaluation regions. The updated cross sections in the URR have reduced capture and total cross sections, which improve agreement with differential measurements compared to ENDF/B-VIII.0, but they deviate slightly further from integral benchmarks. 1 1 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). [Display omitted] • New cross section measurements of 181Ta motivated updates to evaluated cross sections • New evaluations have been performed and included in the ENDF/B-VIII.1 library • The updated 181Ta (n , γ) capture cross section is lower than ENDF/B-VIII.0 • Validation testing showed this was in agreement with differential experimental data • Decreased capture cross section increased reactivity in criticality benchmarks [ABSTRACT FROM AUTHOR]
Copyright of Annals of Nuclear Energy is the property of Pergamon Press - An Imprint of Elsevier Science and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
Database: Engineering Source
Description
Abstract:Nuclear technology applications, including reactor modeling, accelerator design, and isotope production, strongly depend on evaluated nuclear data libraries and their uncertainty information for the assessment of predictive accuracy of calculated quantities. Major nuclear data libraries such as JENDL-5, JEFF-3.3, and ENDF/B-VIII.0 lack uncertainty information for n + 181Ta reactions. In addition to the lack of evaluated uncertainty information even in major nuclear data library releases, the most current US ENDF/B-VIII.0 evaluation of the unresolved resonance region (URR) does not extend to high enough energies to appropriately account for resonance self-shielding effects. This work addresses these shortcomings through a new evaluation of the URR, performed with the SAMMY evaluation tool, which extends the evaluation of the URR to encompass neutron energies of 2.5 keV to 100 keV. This study reports evaluated covariances and includes newly measured data in the evaluation analysis that were unavailable to previous evaluators. The new evaluation was designed to be closely coupled to the resolved resonance region evaluation to improve consistency across multiple evaluation regions. The updated cross sections in the URR have reduced capture and total cross sections, which improve agreement with differential measurements compared to ENDF/B-VIII.0, but they deviate slightly further from integral benchmarks. 1 1 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). [Display omitted] • New cross section measurements of 181Ta motivated updates to evaluated cross sections • New evaluations have been performed and included in the ENDF/B-VIII.1 library • The updated 181Ta (n , γ) capture cross section is lower than ENDF/B-VIII.0 • Validation testing showed this was in agreement with differential experimental data • Decreased capture cross section increased reactivity in criticality benchmarks [ABSTRACT FROM AUTHOR]
ISSN:03064549
DOI:10.1016/j.anucene.2024.111013