Published 1988
| Version v1
Report
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Lithium test module on ITER: engineering design of the tritium recovery system
Description
The design presented is an overview of the tritium recovery system for a lithium module on an ITER type reactor. The design of a tritium recovery system for larger blanket units, sectors, etc. could use the information developed in this report. A goal of this design was to ensure that a reliable, integrated performance of the tritium recovery system could be demonstrated. An equally important goal was to measure and account for the tritium in the liquid lithium blanket module and its recovery system in order to validate the operation of the blanket module
Availability note (English)
Available from NTIS, PC A03/MF A01; 1 as DE88011967.Files
19097229.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 13 p.
- Report number
- CONF-880505--28
Conference
- Title
- 3. topical meeting on tritium technology in fission, fusion and isotopic applications.
- Dates
- 1-6 May 1988.
- Place
- Toronto (Canada).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19097229
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- SPECIFICATIONS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TRITIUM RECOVERY
- Descriptors DEC
- CLOSED PLASMA DEVICES; THERMONUCLEAR DEVICES
Optional Information
- Notes
- Portions are illegible in microfiche products.