Connecting Experimental and Modeling Uncertainties Using Fission Observables

Understanding fission processes presents a challenge due to their complex nature. Our study begins with a comprehensive assessment of the uncertainty of experimental fission cross-section data for 235 U using the template of expected fission cross-section measurement uncertainties to identify missing uncertainties. The code ARIADNE, developed at Los Alamos National Laboratory (LANL), is employed to quantify these experimental uncertainties. This work presents progress towards connecting pre-and post-scission fission modeling with experimental uncertainty quantification for fission cross sections. To this end, the study uses two the-oretical model codes developed at LANL: CoH for modeling 239 Pu fission cross section and the fission event generator CGMF for computing prompt fission observables. The multi-chance fission probability (MCFP) derived from sampling the fission barrier parameters in CoH covering the range of experimental data is utilized as input to CGMF, and its impact on the average prompt fission neutron multiplicity (ν) is examined. The 20% spread in the multi-chance fission probabilities corresponds to a negligible spread in ν of approximately 0.5% at the second-and third-chance fission thresholds.

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Publication Details

Journal
EPJ Web of Conferences
Published
2025-01-01
DOI
https://doi.org/10.1051/epjconf/202532210002
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
0.00

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article

Connecting Experimental and Modeling Uncertainties Using Fission Observables

Denise Neudecker, A. E. Lovell, Fanta Diaby
EPJ Web of Conferences
Nuclear reactor physics and engineering
article

Connecting Experimental and Modeling Uncertainties Using Fission Observables

Denise Neudecker, A. E. Lovell, Fanta Diaby
article en

Abstract

Understanding fission processes presents a challenge due to their complex nature. Our study begins with a comprehensive assessment of the uncertainty of experimental fission cross-section data for 235 U using the template of expected fission cross-section measurement uncertainties to identify missing uncertainties. The code ARIADNE, developed at Los Alamos National Laboratory (LANL), is employed to quantify these experimental uncertainties. This work presents progress towards connecting pre-and post-scission fission modeling with experimental uncertainty quantification for fission cross sections. To this end, the study uses two the-oretical model codes developed at LANL: CoH for modeling 239 Pu fission cross section and the fission event generator CGMF for computing prompt fission observables. The multi-chance fission probability (MCFP) derived from sampling the fission barrier parameters in CoH covering the range of experimental data is utilized as input to CGMF, and its impact on the average prompt fission neutron multiplicity (ν) is examined. The 20% spread in the multi-chance fission probabilities corresponds to a negligible spread in ν of approximately 0.5% at the second-and third-chance fission thresholds.

EPJ Web of ConferencesVol. 322
Los Alamos National Laboratory (US)
U.S. Department of Energy, National Nuclear Security Administration, Los Alamos National Laboratory
Openalex Percentile: Top 94%
Nuclear reactor physics and engineering
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