JENDL project and related activities

Abstract

The latest version of general-purpose file JENDL-4.0 was released in 2010 with improving fission product and minor actinide data as well as covariance data to meet needs of innovative reactors. After the release of JENDL-4.0, efforts to extend energy range up to 200 MeV have been made in order to meet needs from various accelerator applications such as ADS. They were complied with proton induced reaction data into JENDL-4.0/HE and released in 2015. We also released two special purpose files. One is JENDL/PD-2016 which contains the data of photo-nuclear reaction cross sections covering a wide area of the nuclear chart. The other one is JENDL/AD-2017 which provides production cross sections of radioactive nuclei by neutrons. Regarding the general-purpose file, we are planning to release the next version of JENDL, which would be made available in FY2021 as JENDL-5. To contribute to the important problems concerning the nuclear energy in Japan such as nuclear waste and nuclear safety as well as various application fields of nuclear data, it is intended to raise reliability of simulation calculation of nuclear reactors and neutron transportation in structure materials. Nuclear data processing is an important interface between an evaluated nuclear data and nuclear transport calculation codes. The transport codes require cross section library which is generated by a nuclear data processing system. The nuclear data processing system is not just a converter. It performs many processes, e.g., linearization, reconstruction of the resonance region, Doppler broadening, etc. We developed a new nuclear data processing system FRENDY to process evaluated nuclear data files. FRENDY version 1 was released in March 2019 as an open source software under the 2-clause BSD license. FRENDY can be downloaded from JAEA’s web site.