Published March 1976
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Study of tritium removal from fusion reactor blankets of molten salt and lithium--aluminum
Description
The sorption of tritium by molten lithium--bismuth (Li--Bi, approx. 15 at. % lithium) and solid equiatomic lithium--aluminum (Li--Al) was investigated experimentally to evaluate the potential applications of both materials in a controlled thermonuclear reactor. The Li--Bi alloy was proposed to countercurrently extract tritium from a molten salt (Li2BeF4) blanket. However, because of the low solubility (< 10 ppB) at temperature ranging from 500 to 7000C, the extraction process is not attractive
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A05/MF A01.Files
10464490.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 92 p.
- Report number
- ORNL/TM--5104
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10464490
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- ADSORPTION; ALUMINIUM ALLOYS; BREEDING BLANKETS; FLIBE; LITHIUM ALLOYS; MOLTEN SALTS; TRITIUM; TRITIUM RECOVERY
- Descriptors DEC
- ALLOYS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; REACTOR COMPONENTS; SALTS; YEARS LIVING RADIOISOTOPES