Development of multi-group neutron activation cross-section library from JENDL/AD-2017
JENDL Activation Cross Section File for Nuclear Decommissioning 2017 (JENDL/AD-2017)  was released in 2018. This file includes neutron-induced nuclear reaction cross-sections of 311 nuclides from 10-5 eV to 20 MeV. Dr. Okumura et al. developed a multi-group neutron activation cross-section library (MAXS2015) based on the nuclear data libraries JENDL-4.0 and JEFF-3.0/A for activation calculations in nuclear facility decommissioning . Thus a multi-group neutron activation cross-section library (MAXS/AD-2017) with the same format as MAXS-2015 has been developed from JENDL/AD-2017 for activation calculations in nuclear facility decommissioning. >
MAXS-2015 was produced with the NJOY2012  code. However it was found that the groupr module in NJOY2012 could not treat the production cross sections for radionuclides. Then the PREPRO 2018  code was adopted for producing a group-wise file of JENDL/AD-2017. The following modules in PREPRO 2018 were used; ENDF2C, LINEAR, RECENT, SIGMA1, ACTIVATE, FIXUP, DICTIN, GROUPIE. The calculation conditions are as follows,
- Temperature : 300 K
- Group structure : VITAMIN-B6 (199 groups)
- Weight function : Maxwell+1/E+Fission
- Infinite dilution
The produced group-wise file of JENDL/AD-2017 was converted to MAXS/AD-2017 of the MAXS format  with a small program. >
MAXS/AD-2017 will be converted to an ORIGEN-S library and be tested with the JPDR decommissioning data. Then MAXS/AD-2017 will be released. >
 K. Okumura, K. Kojima, K. Tanaka, “Development of multi-group neutron activation cross-section library for decommissioning of nuclear facilities,” Proc. of 2014 Symposium on Nuclear Data, p. 43, JAEA-Conf 2015-003(2016).
 R. E. MacFarlane, D. W. Muir, R. M. Boicourt, A. C. Kahler, “The NJOY Nuclear Data Processing System, Version 2012,” LA-UR-12-27079, Los Alamos National Laboratory (2012).