Open AccessPRELIMINARY EVALUATION OF THE 20% ENRICHED URANIUM CORE FOR THE MATERIALS TESTING REACTOR
Author(s) -
D.R. deBoisblanc,
R.S. Marsden
Publication year - 1958
Language(s) - English
Resource type - Reports
DOI - 10.2172/4340498
Subject(s) - nuclear engineering , cladding (metalworking) , fission products , enriched uranium , nuclear reactor core , fission , uranium , core (optical fiber) , thorium fuel cycle , burnup , decay heat , environmental science , materials science , waste management , nuclear physics , engineering , physics , mox fuel , neutron , composite material
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