An appraisal of deuterium retention in JET and the implications for tritium retention in ITERFunded under: FP3-FUSION 11C
The amounts of deuterium retained within the JET vessel after campaigns in the years 1985-9 have been re-evaluated and shown to indicate that codeposition of D and wall material is the principal retention mechanism. The amount per pulse is shown to fit well with a model wherein the amount of carbon (or other wall material) passing through the plasma during the discharge determines the maximum retention. Such a model can then be used to predict hydrogen isotope retention in other large machines such as ITER. For ITER if a global impurity level in the plasma of 1 % is used, the maximum retention of tritium would be 500 g in 10exp6 secs.
Bibliographic Reference: Report: JET-R(94)11 EN (1994) 18 pp.
Availability: Available from the Publications Officer, JET Joint Undertaking, Abingdon, Oxon. OX14 3EA (GB)
Record Number: 199510212 / Last updated on: 1995-02-21
Original language: en
Available languages: en