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

EXFORユーティリティコード(ForEXy)と中性子核分裂断面積評価への応用

大塚 直彦*; Devi, V.*; 岩本 修  

Otsuka, Naohiko*; Devi, V.*; Iwamoto, Osamu

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.