C. H. Skinner A. A. Haasz V. Kh. Alimov N. Bekris R. A. Causey R. E. H. Clark J. P. Coad J. W. Davis R. P. Doerner M. Mayer A. Pisarev J. Roth T. Tanabe
Management of tritium inventory remains one of the grand challenges in the development of fusion energy, and the choice of plasma-facing materials is a key factor for in-vessel tritium retention. The Atomic and Molecular Data Unit of the International Atomic Energy Agency organized a Coordinated Research Project (CRP) on the overall topic of tritiu…
PublishedA S Kaye H Altmann R Albanese D Ciric P Coad D Brennan F Durodie T Edlington D C Edwards R Felton T T C Jones A Lioure P Lomas J Mailloux I Monakhov M Nightingale J Pamela R Pearce V Riccardo J Rapp A Rolfe E Surrey S Rosanvallon T Todd, A Walden
JET supports ITER both in development of technology and in torus operations. The latter include the study of ITER-like scenarios, operation in tritium (a trace tritium campaign has recently been completed), mitigation of ELMs and disruptions, investigation of tritium retention, real time control of plasma parameters, and control of extreme plasma s…
PublishedT.Tanabe K.Sugiyama C.H.Skinner N.Bekris C.A.Gentile J.P. Coad
Tritium accumulating in codeposits in the gaps between plasma facing components is a safety concern in next step fusion machines as suitable removal techniques have yet not been developed. We report on Imaging Plate measurements of the tritium areal distribution on the side surface of graphite/CFC tiles installed in the TFTR bumper limiter and JET …
PublishedJ.P. Coad M. Rubel N. Bekris D Brennan D. Hole J. Likonen E. Vainonen-Ahlgren EFDA-JET Contributors
JET has operated with divertors of differing geometries since 1994. Impurities accumulated in the inner leg of all the divertors, and operation of the first (Mk I) divertor with beryllium tiles demonstrated that most are eroded from the main chamber walls and swept along the scrape-off layer to the inner divertor. Carbon deposited at the inner dive…
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