Is Carbon a Realistic Choice for ITER's Divertor.

Skinner, C. H. ; Federici, G.

Technical Information Center Oak Ridge Tennessee

关键词: Carbon;    Divertors;    ITER Tokamak;    Plasma;    Retention;   

RP-ID  :  DE2005840424

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

Tritium retention by codeposition with carbon on the divertor target plate is predicted to limit ITERs DT burning plasma operations (e.g. to about 100 pulses for the worst conditions) before the in-vessel tritium inventory limit, currently set at 350 g, is reached. At this point ITER will only be able to continue its burning plasma program if technology is available that is capable of rapidly removing large quantities of tritium from the vessel with over 90% efficiency. The removal rate required is four orders of magnitude faster than that demonstrated in current tokamaks. Eighteen years after the observation of codeposition on JET and TFTR, such technology is nowhere in sight. The inexorable conclusion is that either a major initiative in tritium removal should be funded or that research priorities for ITER should focus on metal alternatives.