Tritium retention in next step devices and the requirements for mitigation and removal techniques

被引:87
作者
Counsell, G. [1 ]
Coad, P.
Grisola, C.
Hopf, C.
Jacob, W.
Kirschner, A.
Kreter, A.
Krieger, K.
Likonen, J.
Philipps, V.
Roth, J.
Rubel, M.
Salancon, E.
Semerok, A.
Tabares, F. L.
Widdowson, A.
机构
[1] UKAEA, EURATOM, Fus Assoc, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
[2] CEA, EURATOM Assoc, DSM, DRFC Cadarache, F-13108 St Paul Les Durance, France
[3] EURATOM, Max Planck Inst Plasmaphys, D-85748 Garching, Germany
[4] Forschungszentrum Julich, EURATOM Assoc, Inst Plasmaphys, Julich, Germany
[5] EURATOM, TEKES, VTT Proc, Espoo 02044, Finland
[6] Royal Inst Technol, Alfven Lab, KTH, Assoc EURATOM VR, S-10044 Stockholm, Sweden
[7] CEA Saclay, DEN, DPC, SCP,LILM, F-91191 Gif Sur Yvette, France
[8] EURATOM, CIEMAT, Lab Nacl Fus, Madrid 28040, Spain
基金
英国工程与自然科学研究理事会;
关键词
D O I
10.1088/0741-3335/48/12B/S18
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
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.
引用
收藏
页码:B189 / B199
页数:11
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