REPROCESSING FAST REACTOR FUELS AT DOUNREAY
The reprocessing of advanced fuels such as carbides, oxides, and cermets, containing up to 30% Pu was studied. Dissolution of uranium carbides in nitric acid produces appreciable quantities of mellitic acid that has undesirable effects in subsequent stages of the process. Mixed oxides containing up to about 40% Pu in solid solution with UO/sub 2/ are soluble in nitric acid and a leaching type process in nitric acid for a stainless steel/UO/sub 2/. PuO/sub 2/ fuel containing 30% Pu appears to be feasible. It offers considerable economic advantages over total dissolution routes. A new oxidation-sublimation process is described for metallic fuels containing up to 12% Mo. New data are presented on the solvent extraction of U and Pu nitrates into tributyl phosphate-odorless kerosene and of the influence of radiolytically produced acid phosphates on this part of the process. It was concluded that there are no insuperable difficuities that will prevent the satisfactory reprocessing of high burn-up Pu fuels by a solvent extraction route. (auth)
- Research Organization:
- United Kingdom Atomic Energy Authority, Thurso, Caithness, Scotland
- NSA Number:
- NSA-17-020123
- OSTI ID:
- 4722487
- Journal Information:
- Trans. AIME, Journal Name: Trans. AIME Vol. Vol: 227
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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Related Subjects
CARBIDES
CERMETS
CHEMISTRY
DECOMPOSITION
ECONOMICS
EVAPORATION
KEROSENE
LEACHING
MELLITIC ACID
MOLYBDENUM ALLOYS
NITRIC ACID
ORGANIC ACIDS
OXIDATION
OXIDES
PETROLEUM
PHOSPHATES
PLUTONIUM
PLUTONIUM NITRATES
PLUTONIUM OXIDES
RADIATION CHEMISTRY
REPROCESSING
SOLID SOLUTIONS
SOLUTIONS
SOLVENT EXTRACTION
STAINLESS STEELS
SUBLIMATION
URANIUM CARBIDES
URANIUM DIOXIDE
URANIUM NITRATES
WASTE PROCESSING