EXFOR-based simultaneous evaluation for neutron-induced fission cross section of plutonium-242

Abstract

The ${}^{242}$Pu neutron-induced fission cross section was evaluated from 100 keV to 200 MeV. The experimental ${}^{242}$Pu and ${}^{235}$U fission cross sections and their ratios in the EXFOR library were reviewed and analysed by the least-squares method. Additional simultaneous evaluation was performed by including the experimental database of the ${}^{233,238}$U and ${}^{239,240,241}$Pu fission cross sections and their ratios developed for JENDL-5 evaluation. The ${}^{242}$Pu fission cross sections from our evaluation and JENDL-5 evaluation are close to each other below 1 MeV while systematically differ from each other above 10 MeV. The cross section from our evaluation is systematically lower than the JENDL-4.0 cross section in the prompt fission neutron spectrum peak region ($\sim$5% lower around 1 MeV). The newly evaluated ${}^{242}$Pu fission cross section was verified against the cross section measured in the ${}^{252}$Cf spontaneous fission neutron field and criticalities of small-sized LANL fast systems, and demonstrated better performance than the JENDL-4.0 cross section on the same level with the JENDL-5 cross section.

arXiv commentSubmitted to Journal of Nuclear Science and Technology

References in corpus (4)

• Towards a More Complete and Accurate Experimental Nuclear Reaction Data Library (EXFOR): International Collaboration Between Nuclear Reaction Data Centres (NRDC)
• IRDFF-II: A New Neutron Metrology Library
• Measurement of the 235U(n,f) cross section relative to the 6Li(n,t) and 10B(n,alpha) standards from thermal to 170 keV neutron energy range at n_TOF
• EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5

Cited by in corpus (2)

• Evaluation of uranium-233 neutron capture cross section in keV region
• EXFOR utility codes (ForEXy) and their application to neutron fission cross section evaluation