Tritium saturation in plasma-facing materials surfaces

被引:12
作者
Longhurst, GR [1 ]
Anderl, RA
Causey, RA
Federici, G
Haasz, AA
Pawelko, RJ
机构
[1] Idaho Natl Engn & Environm Lab, Idaho Falls, ID USA
[2] Sandia Natl Labs, Livermore, CA USA
[3] ITER Garching Joint Work Site, Garching, Germany
[4] Univ Toronto, Inst Aerosp Studies, Toronto, ON, Canada
关键词
D O I
10.1016/S0022-3115(98)00112-3
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Plasma-facing components in the International Thermonuclear Experimental Reactor (ITER) will experience, high heat loads and intense plasma fluxes of order 10(20)-10(23) particles/m(2)s. Experiments on Be and W, two of the materials considered for use in ITER, have revealed that a tritium saturation phenomenon can take place under these conditions in which damage to the surface results that enhances the return of implanted tritium to the plasma and inhibits uptake of tritium. This phenomenon is important because it implies that tritium inventories due to implantation in these plasma-facing materials will probably be lower than was previously estimated using classical recombination-limited release at the plasma surface. Similarly, permeation through these components to the coolant streams should be re duced. In this paper we discuss evidences for the existence of this phenomenon, describe techniques for modeling it, and present results of the application of such modeling to prior experiments. (C) 1998 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:640 / 644
页数:5
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