Published January 1984
| Version v1
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Assessment of problems associated with tritium containment
Description
Preventing tritium leakage across a large heat transfer area at high temperature is one of the most difficult problems associated with a D-T fusion reactor design. One of the most efficient methods to reduce the mobility of tritium is to convert it to tritiated water. Most solid breeder systems use a purge gas and assume tritium will be oxidized into the water form. For 17 Li-83Pb system, a double-walled steam generator is used. Tritium is assumed to be oxidized across the gap in between the two walls. However, if tritium cannot be oxidized efficiently, the tritium containment problem can become critical
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE84006441.Files
15071172.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 4 p.
- Report number
- CONF-840614--26
Conference
- Title
- Annual meeting of the American Nuclear Society.
- Dates
- 3-8 Jun 1984.
- Place
- New Orleans, LA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15071172
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT; DIFFUSION; LEAD ALLOYS; LITHIUM ALLOYS; OXIDATION; PERMEABILITY; STEAM GENERATORS; TRITIUM
- Descriptors DEC
- ALLOYS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; BOILERS; CHEMICAL REACTIONS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; VAPOR GENERATORS; YEARS LIVING RADIOISOTOPES