Tritium in fusion power reactor blankets
Journal Article
·
· Nucl. Technol., v. 21, no. 1, pp. 39-49
OSTI ID:4365158
Several related problems involving the recovery of tritium from the breeding blanket in fusion power reactors are considered. They include the use of stagnant lithium blankets, the use of lithium as a regenerable getter pump, and the use of breeder materials that are lithium intermetallic alloys. Transient tritium recovery rates during startup are also estimated. Keeping the tritium inventory low and providing an economical recovery cycle are conflicting goals. These topics may provide a scheme by which both might be accomplished. (auth)
- Research Organization:
- Univ. of California, Livermore
- NSA Number:
- NSA-29-014456
- OSTI ID:
- 4365158
- Journal Information:
- Nucl. Technol., v. 21, no. 1, pp. 39-49, Journal Name: Nucl. Technol., v. 21, no. 1, pp. 39-49; ISSN NUTYB
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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