EXFOR utility codes (ForEXy) and their application to neutron fission cross section evaluation

We developed a set of EXFOR utility codes (ForEXy) to process the information of the experimental nuclear reaction data stored in the EXFOR library. We designed a new JSON format (J4) for the EXFOR library, and developed a code converting the information in an EXFOR file to a J4 file (X4TOJ4) and another code converting it to an EXFOR file (J4TOX4) as a core part of this new code package. We also developed some other codes for management of the EXFOR storage, bibliography and dictionary. As an application of the new code package, we constructed covariance matrices for the fast neutron induced fission cross sections of neptunium-237 in the EXFOR library by using the new codes, and applied them to evaluation of the cross section between 100 keV and 200 MeV.

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Publication Details

Journal
Applied Radiation and Isotopes
Published
2025-05-29
DOI
https://doi.org/10.1016/j.apradiso.2025.111903
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
0.00
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article

EXFOR utility codes (ForEXy) and their application to neutron fission cross section evaluation

Vidya Devi, Naohiko Otuka, Osamu Iwamoto
Applied Radiation and Isotopes
Nuclear reactor physics and engineering
article

EXFOR utility codes (ForEXy) and their application to neutron fission cross section evaluation

Vidya Devi, Naohiko Otuka, Osamu Iwamoto
article en

Abstract

We developed a set of EXFOR utility codes (ForEXy) to process the information of the experimental nuclear reaction data stored in the EXFOR library. We designed a new JSON format (J4) for the EXFOR library, and developed a code converting the information in an EXFOR file to a J4 file (X4TOJ4) and another code converting it to an EXFOR file (J4TOX4) as a core part of this new code package. We also developed some other codes for management of the EXFOR storage, bibliography and dictionary. As an application of the new code package, we constructed covariance matrices for the fast neutron induced fission cross sections of neptunium-237 in the EXFOR library by using the new codes, and applied them to evaluation of the cross section between 100 keV and 200 MeV.

Applied Radiation and IsotopesVol. 225
Japan Atomic Energy Agency (JP), International Atomic Energy Agency (AT), Panjab University (IN)
Openalex Percentile: Top 84%
Nuclear reactor physics and engineering
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