Dissolution of FFTF vendor fuel

Conference · Wed Aug 01 00:00:00 EDT 1979

OSTI ID:5840714

Lerch, R. E.

Dissolution experiments were performed on FFTF vendor fuel (both mechanically mixed and coprecipitated) during 1974, 1975, and 1976. A marked improvement was noted in the completeness of fuel dissolution from 1974 to 1976. The reason for this is unknown but may have been attributable to slight changes in fuel fabrication conditions. In general, the bulk of the fuel pellets tested dissolved to greater than 99.9% in nitric acid alone.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: EY-76-C-14-2170
• OSTI ID: 5840714
• Report Number(s): HEDL-SA-1931; CONF-791086-2
• Country of Publication: United States
• Language: English

Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDE COMPOUNDS
CHALCOGENIDES
DISSOLUTION
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL CYCLE
FUEL PELLETS
HYDROGEN COMPOUNDS
INORGANIC ACIDS
LIQUID METAL COOLED REACTORS
NITRIC ACID
OXIDES
OXYGEN COMPOUNDS
PELLETS
PLUTONIUM COMPOUNDS
PLUTONIUM DIOXIDE
PLUTONIUM OXIDES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES