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Tritium recovery in ITER by radiative plasma terminations
被引:27
|作者:
Whyte, DG
Davis, JW
机构:
[1] Univ Wisconsin, Madison, WI 53706 USA
[2] Univ Toronto, Inst Aerosp Studies, N York, ON M3H 5T6, Canada
关键词:
tritium;
desorption;
hydrogen inventory;
ablation;
D O I:
10.1016/j.jnucmat.2004.10.134
中图分类号:
T [工业技术];
学科分类号:
08 ;
摘要:
Planned radiative plasma terminations are examined as a method to recover tritium from plasma-deposited layers in the ITER tokamak. The technique exploits the high energy density of the ITER plasma, which is converted into a quasi-uniform radiation pulse by massive impurity injection that benignly terminates the plasma discharge. The radiation pulse transiently heats all plasma-viewing surfaces in order to desorb the tritium, which is released into the vessel and recovered by pumping. Calculations indicate significant tritium removal at reduced plasma current, similar to 6-10 MA, indicating the possibility of routine T recovery during the current rampdown phase of each discharge or during low current tritium recovery discharges. (c) 2004 Elsevier B.V. All rights reserved.
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页码:560 / 564
页数:5
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