Published October 1983
| Version v1
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Evaluation of a spent fuel as a waste form in a salt repository
Description
Leach tests have been performed on spent fuel in sythetic Permian Basin salt brine at 25 and 750C. Complementary tests on unirradiated UO2 pellets have been conducted in both salt brine and deionized water in the range 25 to 1500C. Iron and/or oxidized zircaloy coupons were included in some of the tests. Uranium release from spent fuel was more than 100 times greater than from UO2. In brine, iron had no significant effect on the total uranium release but substantially reduced the amount in solution by causing the uranium to plate out on the iron coupon and container walls and to precipitate as filterable particles
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE84003343.
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The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 15 p.
- Report number
- PNL-SA--11770
Conference
- Title
- Materials Research Society annual meeting.
- Dates
- 14-17 Nov 1983.
- Place
- Boston, MA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15025790
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ALLOY-ZR98SN-4; BRINES; CORROSION; EXPERIMENTAL DATA; HIGH TEMPERATURE; IRON; LEACHING; MEDIUM TEMPERATURE; RADIOACTIVE WASTE DISPOSAL; SALT DEPOSITS; SPENT FUELS; TEXAS; URANIUM; URANIUM DIOXIDE; WATER
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; ALLOYS; CHALCOGENIDES; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CORROSION RESISTANT ALLOYS; DATA; DEVELOPED COUNTRIES; DISSOLUTION; ELEMENTS; ENERGY SOURCES; FUELS; GEOLOGIC DEPOSITS; HEAT RESISTING ALLOYS; HYDROGEN COMPOUNDS; INFORMATION; IRON ADDITIONS; MANAGEMENT; MATERIALS; METALS; NORTH AMERICA; NUCLEAR FUELS; NUMERICAL DATA; OXIDES; OXYGEN COMPOUNDS; REACTOR MATERIALS; SEPARATION PROCESSES; TIN ALLOYS; TRANSITION ELEMENTS; URANIUM COMPOUNDS; URANIUM OXIDES; USA; WASTE DISPOSAL; WASTE MANAGEMENT; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Secondary number(s)
- CONF-831174--25.