PRODUCTION OF REACTOR FUEL OXIDES FROM MOLTEN CHLORIDE SALT SOLUTIONS

Autor:	F A Scott, L K Mudge, G E Benedict, K M Harmon, G Jansen
Rok vydání:	1963
Předmět:	chemistry.chemical_compound chemistry Uranium dioxide Inorganic chemistry Oxide Irradiation Chloride salt Electrochemistry Chemical reaction Dissolution Nuclear chemistry Solid solution
DOI:	10.2172/4692951
Popis:	Laboratory and engineering scale studies on the dissolution of irradiated oxide fuels in a molten chloride salt solution, and recovery of U, Th, and Pu as their oxides by appropriate electrochemical or chemical reactions are described. Exploratory studies on the preparation of PuC/sub 2/-UO/sub 2/, PuO/ sub 2/-- ThO/sub 2/, and UO/sub 2/-- ThO/sub 2/ solid solutions b y reaction in molten chloride salt solutions are also discussed. (P.C.H.)
Databáze:	OpenAIRE
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