Review of tritium retention in first wall materialsFunded under: FP3-FUSION 11C
This paper reviews the hydrogen and tritium retention properties of materials used in tokamaks. Stainless steel, inconel and graphite, which are the main constituents of present day tokamaks, are discussed and also beryllium, which has been used for certain applications in tokamaks. Estimates are made of the hydrogen retention for the ITER first wall for which vanadium-based alloys are a candidate material.
Bibliographic Reference: Report: JET-P(93)93 EN (1993) 16 pp.
Availability: Available from the Publications Officer, JET Joint Undertaking, Abingdon, Oxon. OX14 3EA (GB)
Record Number: 199410617 / Last updated on: 1994-11-28
Original language: en
Available languages: en