Open AccessLiterature review of United States utilities computer codes for calculating actinide isotope content in irradiated fuel
Author(s) -
W.C. Horak,
Ming-Shih Lu
Publication year - 1991
Language(s) - English
Resource type - Reports
DOI - 10.2172/10143291
Subject(s) - actinide , nuclear engineering , code (set theory) , isotope , content (measure theory) , key (lock) , computer science , nuclear physics , physics , engineering , mathematics , computer security , set (abstract data type) , programming language , mathematical analysis