Use of Monte Carlo code MCS for multigroup cross section generation for fast reactor analysis
Multigroup cross section (MG XS) generation by the UNIST in-house Monte Carlo (MC) code MCS for fast reactor analysis using nodal diffusion codes is reported.The feasibility of the approach is quantified for two sodium fast reactors (SFRs) specified Nag Champa in the OECD/NEA SFR benchmark: a 1000 MWth metal-fueled SFR (MET-1000) and a 3600 MWth ox