Open AccessProcess technology for the molten-salt reactor $sup 233$U--Th cycle
Author(s) -
J.R. Jr. Hightower
Publication year - 1975
Language(s) - English
Resource type - Reports
DOI - 10.2172/4129264
Subject(s) - molten salt , fuel cycle , breeder (animal) , molten salt reactor , liquid fluoride thorium reactor , uranium 233 , nuclear engineering , process (computing) , fission , process engineering , fission products , waste management , engineering , materials science , computer science , radiochemistry , plutonium , nuclear reactor , chemistry , nuclear physics , metallurgy , mox fuel , physics , blanket , operating system , composite material , neutron
After a brief description of the design features of the molten-salt breeder reactor, fuel processing for removal of $sup 233$Pa and fission products is examined. Some recent developments in processing technology are discussed. (JWR
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