Material erosion at the vessel walls of future fusion devices

被引:129
作者
Behrisch, R
Federici, G
Kukushkin, A
Reiter, D
机构
[1] Max Planck Inst Plasma Phys, EURATOM Assoc, D-85748 Garching, Germany
[2] ITER, D-85748 Garching, Germany
[3] Forschungszentrum Julich, Inst Plasma Phys, D-52425 Julich, Germany
关键词
sputtering; beryllium; tungsten; carbon; tokamaks;
D O I
10.1016/S0022-3115(02)01580-5
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
For a next-step fusion device the erosion at the vessel walls during normal operation caused by the bombardment with different species from the plasma is estimated. The wall fluxes are calculated for a given 'burning' plasma with the computer code B2-EIRENE. With the known sputtering yields the erosion rates for vessel walls made out of Be, Q Fe, Mo or W, are calculated. The erosion by ions is found to be of the same order of magnitude as the erosion by energetic neutrals. The erosion has minima around the area of gas feed and maxima close by and at the bottom near the baffles of the divertor. The calculated total erosion is of the order of 10(21) to 10(22) atom/s for low Z materials, and a factor 10-20 lower for high Z materials, such as W, resulting in about 5 kg per full-day of operation or 1 t/y. (C) 2003 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:388 / 392
页数:5
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