Tritium retention in next step devices and the requirements for mitigation and removal techniques
2006 (English)In: Plasma Physics and Controlled Fusion, ISSN 0741-3335, E-ISSN 1361-6587, Vol. 48, no 12B, B189-B199 p.Article in journal (Refereed) Published
Mechanisms underlying the retention of fuel species in tokamaks with carbon plasma-facing components are presented, together with estimates for the corresponding retention of tritium in ITER. The consequential requirement for new and improved schemes to reduce the tritium inventory is highlighted and the results of ongoing studies into a range of techniques are presented, together with estimates of the tritium removal rate in ITER in each case. Finally, an approach involving the integration of many tritium removal techniques into the ITER operational schedule is proposed as a means to extend the period of operations before major intervention is required.
Place, publisher, year, edition, pages
2006. Vol. 48, no 12B, B189-B199 p.
fusion devices, re-deposition, jet, carbon, suppression, inventory, oxygen, layers
IdentifiersURN: urn:nbn:se:kth:diva-16180DOI: 10.1088/0741-3335/48/12B/S18ISI: 000242552600020ScopusID: 2-s2.0-34249896555OAI: oai:DiVA.org:kth-16180DiVA: diva2:334222
QC 20100525, QC 20110929. Conference: 33rd European-Physical-Society Conference on Plasma Physics. Angelicum Univ, Rome, ITALY. JUN 19-23, 2006 2010-08-052010-08-052011-09-29Bibliographically approved