Nuclear Data Uncertainty Quantification of High Flux Isotope Reactor Low-Enriched Uranium Design

D. Hartanto, J. W. Bae, B. R. Betzler, J. R. Burns, D. Chandler, C. Sizemore

Research output: Contribution to journalConference articlepeer-review

Abstract

The sensitivity analysis and uncertainty quantification studies have been performed in support of ongoing validation efforts to strengthen the understanding and confidence in the use of LEU core design study tools to predict core behavior and performance. The results of this sensitivity analysis reveal the top positive sensitivity contributions from 235U ν̅, 1H (n, el.), 235U (n, f), 27Al (n, el.), and 16O (n, el.). Meanwhile, the top negative sensitivity contributions are from 235U (n, γ)ǡ 238U (n, γ), 1H (n, γ), 27Al (n, γ), and 10B (n, α). Moreover, the uncertainty of the three HFIR LEU silicide cores is comparable-about 0.6 %Δkeff/keff. It is similar to the uncertainty of the current HFIR HEU, which is also about 0.6 %Δkeff/keff. To reduce the uncertainty, the accuracy of nuclear data for 1H, 27Al, 235U, and 238U must be improved. Finally, the similarity coefficient indicates that about 200 critical experiments can be leveraged for the design validation efforts of HFIR LEU. The trending analysis can be further explored in a future work to determine the bias and bias uncertainty of the HFIR LEU computational tool and nuclear data.

Original languageEnglish
Pages (from-to)792-795
Number of pages4
JournalTransactions of the American Nuclear Society
Volume128
DOIs
StatePublished - 2023
Event2023 Transactions of the American Nuclear Society Annual Meeting and Technology Expo, ANS 2023 - Indianapolis, United States
Duration: Jun 11 2023Jun 14 2023

Funding

1 Notice: This manuscript has been authored by UT-Battelle LLC under Contract No. DE-AC05-00OR22725 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The Department of Energy 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). This material is based upon work supported and funded by the U.S. Department of Energy National Nuclear Security Administration’s Office of Material Management and Minimization. This research was performed on the High Flux Isotope Reactor, a US DOE Office of Science User Facility operated by ORNL under contract DE-AC05-00OR22725.

FundersFunder number
U.S. Department of Energy
Office of Science
National Nuclear Security Administration
Oak Ridge National LaboratoryDE-AC05-00OR22725
UT-Battelle

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