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Abstract

During the JET preliminary tritium experiment (PTE), an estimated 2 x 1.0 E12 Bq (1.1 x 1.0 E21 atoms) of tritium was injected into the JET vacuum vessel. Experiments were then performed to: (i) assay the tritium remaining in the first wall; (ii) study methods of tritium removal; (iii) arrive at an understanding of the processes involved. The results of the experiments may permit predictions of tritium inventories and their removal rates for the JET tritium phase and for other D-T fuelled tokamaks. The PTE is described to give an estimate of the torus tritium inventory prior to the release experiments. A functional description of the recovery and monitoring system is given, together with an outline of the neutron measurements used to obtain plasma tritium-to-deuterium ratios during the post-PTE period. The tritium release experiments are then detailed with the results and their interpretation also being presented. A new physical model is described which includes both ion implantation into a surface layer and diffusion of tritium into the bulk material. Finally, the conclusions of this work are presented.

Additional information

Authors: ANDREW P ET AL., JET Joint Undertaking, Abingdon, Oxon. (GB);GOODALL D J H, AEA Fusion, Culham Laboratory, Abingdon, Oxon. (GB);MCCRACKEN G M, AEA Fusion, Culham Laboratory, Abingdon, Oxon. (GB)
Bibliographic Reference: Report: JET-P(93)08 EN (1993) 28 pp.
Availability: Available from the Publications Officer, JET Joint Undertaking, Abingdon, Oxon. OX14 3EA (GB)
Record Number: 199310601 / Last updated on: 1994-11-29
Category: PUBLICATION
Original language: en
Available languages: en