Open AccessHigh Temperature Gas-Cooled Reactor Criticality Research Program
Author(s) -
S.R. Bierman,
E.D. Clayton
Publication year - 1976
Language(s) - Uncategorized
Resource type - Reports
DOI - 10.2172/7125694
Subject(s) - criticality , thorium , nuclear engineering , nuclear data , enriched uranium , uranium , isotopes of uranium , uranium 235 , nuclear physics , uranium 233 , thorium fuel cycle , neutron , actinide , fuel cycle , environmental science , physics , engineering , neutron temperature , mox fuel
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