FENDL/MG-1.0. Library of multigroup cross sections in GENDF and MATXS format for neutron-photon transport calculations generated by R.R. MacFarlane by processing FENDL/E-1. Summary documentation

摘要

Selected neutron reaction nuclear data evaluations and photon-atomic interaction cross section libraries for elements of interest to the IAEA's program on Fusion Evaluated Nuclear Data Library (FENDL) have been processed into GENDF and MATXS format using the NJOY system by R.E. MacFarlane. This document summarizes the resulting multigroup data library FENDL/MG-1.0. The data are available costfree, upon request from the IAEA Nuclear Data Section, online or on magnetic tape. (author). 6 refs. (Atomindex citation 26:070578)