Tritium recycling and retention in JET

被引:82
作者
Andrew, P [1 ]
Brennan, D
Coad, JP
Ehrenberg, J
Gadeberg, M
Gibson, A
Groth, M
How, J
Jarvis, ON
Jensen, H
Lässer, R
Marcus, F
Monk, R
Morgan, P
Orchard, J
Peacock, A
Pearce, R
Pick, M
Rossi, A
Schunke, B
Stamp, M
von Hellermann, M
Hillis, DL
Hogan, J
机构
[1] JET Joint Undertaking, Abingdon OX14 3EA, Oxon, England
[2] Oak Ridge Natl Lab, Oak Ridge, TN USA
关键词
tritium retention; wall pumping; JET;
D O I
10.1016/S0022-3115(98)00662-X
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
JET's 1997 Deuterium Tritium Experiment (DTE1) allows a detailed study of hydrogenic isotope recycling and retention in a pumped divertor configuration relevant to ITER. There appear to be two distinct forms of retained tritium. (1) A dynamic inventory which controls the fueling behaviour of a single discharge, and in particular determines the isotopic composition. This is shown to be consistent with neutral particle implantation over the whole vessel surface area. (2) A continually growing inventory, which plays a small role in the particle balance of a single discharge, but ultimately dominates the hydrogenic inventory for an experimental campaign comprising thousands of pulses. This will be the dominant retention mechanism in long-pulse devices like ITER. The JET retention scaled-up to ITER proportions suggests that ITER may reach its tritium inventory limit in less than 100 pulses. (C) 1999 JET Joint Undertaking, published by Elsevier Science B.V. All rights reserved.
引用
收藏
页码:153 / 159
页数:7
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