Open AccessDevelopment of Linkage Program Code OpenMC and ORIGEN2.2 for Neutronic Analysis and Burnup Nuclear Reactor Program
Author(s) -
Muhammad Ilham
Publication year - 2022
Publication title -
journal of physics. conference series
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.21
H-Index - 85
eISSN - 1742-6596
pISSN - 1742-6588
DOI - 10.1088/1742-6596/2328/1/012003
Subject(s) - burnup , neutron transport , benchmark (surveying) , linkage (software) , nuclear engineering , monte carlo method , computer science , code (set theory) , nuclear data , nuclear physics , physics , neutron , engineering , chemistry , programming language , mathematics , geology , statistics , biochemistry , geodesy , set (abstract data type) , gene