Abstract
A neutron cross-section evaluation for the n + 103Rh reaction in the resolved resonance region was carried out in the energy range 10−5 eV to 8 keV encompassing thermal energy at 0.0253 eV. The scope of this work is to generate resonance parameters and resonance parameter covariances based on the Reich-Moore reduced R-matrix formalism using the code SAMMY. Some features of the new evaluation are the inclusion of high-resolution capture data in the SAMMY evaluation process and the extension of the resolved resonance range from 4 to 8 keV. Furthermore, the evaluation employs more accurate resonance parameter representation by exploring the use of the LRF = 7 ENDF feature and also the use of the LCOMP = 2 compact format for resonance parameter covariance representation. Included in the SAMMY evaluation are transmission data, capture cross-section data, and neutron scattering length information. Thermal cross-section values listed in the literature, as well as capture resonance integrals, were also incorporated into the evaluation process.
| Original language | English |
|---|---|
| Pages (from-to) | 1045-1061 |
| Number of pages | 17 |
| Journal | Nuclear Science and Engineering |
| Volume | 199 |
| Issue number | 7 |
| DOIs | |
| State | Published - 2025 |
Funding
This work was supported by the Nuclear Criticality Safety Program, funded and managed by the National Nuclear Security Administration for the DOE. Part of this work was carried out when the first author, Luiz Leal, was at the IRSN. Additionally, this work is part of an action sheet under the EURATOM/DOE agreement. This paper has been authored by UTBattelle, LLC, under contract DEAC0500OR22725 with the U.S. Department of Energy (DOE). The U.S. government retains and the publisher, by accepting this paper for publication, acknowledges that the U.S. government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this paper, or allow others to do so, for U.S. government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (https://www.energy.gov/doe-public-access-plan). This paper has been authored by UTBattelle, LLC, under contract DEAC0500OR22725 with the U.S. Department of Energy (DOE). The U.S. government retains and the publisher, by accepting this paper for publication, acknowledges that the U.S. government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this paper, or allow others to do so, for U.S. government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan ( https://www.energy.gov/doe-public-access-plan ).
Keywords
- Nuclear data
- data evaluation
- differential and integral data
- uncertainty
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