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Dissolution rates of as-received and partially oxidized spent fuel

Conference ·
OSTI ID:5664828
; ;
Dissolution rates have been measured for spent fuel in both unoxidized and partially air-oxidized conditions (oxygen-to-metal ratio of 2.4 with U{sub 4}O{sub 9} crystallographic structure), as well as for unirradiated UO{sub 2} and UO{sub 2} that was partially oxidized to U{sub 3}O{sub 7}. All measurements were taken in flow-through tests where uranium concentrations were maintained well below solubility limits to avoid suppression of the measured dissolution rates by solubility constraints. No significant differences in dissolution behavior were found between the oxidized and unoxidized spent fuel or between unirradiated UO{sub 2} and U{sub 3}O{sub 7}.
Research Organization:
Pacific Northwest Lab., Richland, WA (United States)
Sponsoring Organization:
DOE; USDOE, Washington, DC (United States)
DOE Contract Number:
AC06-76RL01830
OSTI ID:
5664828
Report Number(s):
PNL-SA-20371; CONF-920430--77; ON: DE92012348
Country of Publication:
United States
Language:
English

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Related Subjects

052002* -- Nuclear Fuels-- Waste Disposal & Storage
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ACTINIDE COMPOUNDS
ALKALI METAL ISOTOPES
ALKALINE EARTH ISOTOPES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CESIUM 137
CESIUM ISOTOPES
CHALCOGENIDES
CHEMICAL REACTIONS
DISSOLUTION
ENERGY SOURCES
EVEN-EVEN NUCLEI
FUELS
GROUND WATER
HOURS LIVING RADIOISOTOPES
HYDROGEN COMPOUNDS
INTERMEDIATE MASS NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
MANAGEMENT
MATERIALS
NUCLEAR FUELS
NUCLEI
ODD-EVEN NUCLEI
OXIDATION
OXIDES
OXYGEN COMPOUNDS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE MANAGEMENT
RADIOISOTOPES
REACTOR MATERIALS
SPENT FUELS
STRONTIUM 90
STRONTIUM ISOTOPES
TECHNETIUM 99
TECHNETIUM ISOTOPES
UNDERGROUND FACILITIES
URANIUM COMPOUNDS
URANIUM OXIDES
WASTE DISPOSAL
WASTE MANAGEMENT
WATER
YEARS LIVING RADIOI
YEARS LIVING RADIOISOTOPES