Tritium recovery from lithium oxide pellets
The TFTR Lithium Blanket Module is an assembly containing 650 kg of lithium oxide that will be used to test the ability of neutronics codes to model the tritium breeding characteristics of limited-coverage breeding zones in a tokamak. It is required that tritium concentrations as low as 0.1 nCi/g bred in both metallic lithium samples and lithium oxide pellets be measured with an uncertainty not exceeding +- 6%. A tritium assay technique for the metallic samples which meets this criterion has been developed. Two assay techniques for the lithium oxide pellets are being investigated. In one, the pellets are heated in a flowing stream of hydrogen, while in the other, the pellets are dissolved in 12 M hydrochloric acid.
- Research Organization:
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- DOE Contract Number:
- AC02-76CH03073
- OSTI ID:
- 5341585
- Report Number(s):
- PPPL-EPRI-11; ON: DE84006280
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
LITHIUM OXIDES
TRITIUM RECOVERY
BREEDING
BREEDING BLANKETS
NEUTRON TRANSPORT
TFTR REACTORS
TRITIUM
ALKALI METAL COMPOUNDS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CHALCOGENIDES
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
LITHIUM COMPOUNDS
NEUTRAL-PARTICLE TRANSPORT
NUCLEAR FUEL CONVERSION
NUCLEI
ODD-EVEN NUCLEI
OXIDES
OXYGEN COMPOUNDS
RADIATION TRANSPORT
RADIOISOTOPES
REACTOR COMPONENTS
RECOVERY
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
YEARS LIVING RADIOISOTOPES
700206* - Fusion Power Plant Technology- Environmental Aspects