Technical aspects of the first JET tritium experiment
β Scribed by M. Huguet; A.C. Bell; S.J. Booth; C. Caldwell-Nichols; A. Carmichael; P. Chuilon; N. Davies; K.J. Dietz; F. Delvart; F. Erhorn; H. Falter; B.J. Green; B. Grieveson; R. Haange; A. Haigh; J.L. Hemmerich; D. Holland; J. How; T.T.C. Jones; R. Laesser; M. Laveyry; J. Lupo; A. Miller; P. Milverton; G. Newbert; J. Orchard; A. Peacock; R. Russ; G. Saibene; R. Sartori; L. Serio; R. Stagg; S.L. Svensson; E. Thompson; P. Trevalion; E. Usselmann; T. Winkel; M.E.P. Wykes
- Publisher
- Elsevier Science
- Year
- 1992
- Tongue
- English
- Weight
- 947 KB
- Volume
- 19
- Category
- Article
- ISSN
- 0920-3796
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β¦ Synopsis
for the first time a controlled fusion experiment involving mixed deuterium/tritium plasmas was carried out resulting in the release of a peak D-T fusion power of approximately 1.7 MW. The preparations for this First Tritium Experiment, the equipment used for introduction of the tritium and the collection of the exhaust gas as well as the implementation of the experiment and the subsequent clean-up phase are described.
π SIMILAR VOLUMES
Gas recovery during the first JET tritium experiment was mainly based on the use of a cryopump designed earlier [1] for collection of torus exhaust gas. This cryopump system was extended to include collection of gas from the neutral injectors and to provide sampling and diagnostic facilities such as