Published January 1976
| Version v1
Report
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Scoping studies of tritium handling in a tokamak experimental power reactor
Description
Tritium handling techniques in an experimental fusion power reactor (EPR) are evaluated to determine the requirements of the system and to compare different equipment and techniques for meeting those requirements. Tritium process equipment is needed (1) to evacuate and maintain a vacuum in the plasma vessel and the neutral beam injectors, (2) to purify and recycle tritium and deuterium for the plasma fuel cycle, (3) to recover tritium from experimental breeding modules, and (4) to provide tritium containment and atmospheric cleanup. A development program is outlined to develop and demonstrate the required techniques and equipment and to permit confident design of an EPR for operation by the mid-1980s
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS.Files
7246778.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 50 p.
- Report number
- ORNL-TM--5080
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 7246778
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- BREEDING; MATERIALS HANDLING; RADIATION HAZARDS; SAFETY; TOKAMAK DEVICES; TRITIUM
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CLOSED PLASMA DEVICES; HAZARDS; HEALTH HAZARDS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; NUCLEAR FUEL CONVERSION; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; THERMONUCLEAR DEVICES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- Available from NTIS. $5.50.