Erosion/redeposition analysis of lithium-based liquid surface divertors.

Brooks, J. N. ; Rognlien, R. ; Ruzic, D. N. ; Allain, J. P.

Technical Information Center Oak Ridge Tennessee

关键词: Divertors;    Plasma;    Lithium;    Erosion;    Liquids;   

RP-ID  :  DE2001757534

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

An erosion redeposition analysis was performed for three candidate tokamak fusion reactor liquid divertor surfaces-lithium, tin-lithium and flibe (liF+BeF2 salt). The analysis uses coupled edge-plasma, impurity-transport, and sputtering codes (UEDG/WBC/VFTRIM), and available sputtering data. A pure-lithium surface strongly absorbs impinging D-T ions-this results, in a high temperature, low density, low-recycle plasma edge regime. Lithium appears to perform well in this regime. Although overall sputtering is high, self-sputtering is finite. Most (95%) of the sputtered lithium is confined to the near-surface region and redeposited on the divertor with the remainder (5%) also being redeposited after transport in the scrape off layer. Lithium core plasma contamination potential is low. Tin-lithium and flibe would likely operate in a high-recycle regime. Erosion/redeposition performance of these materials is also good, with finite self-sputtering and negligible core plasma contamination predicted, but with some potential for changing surface composition due to different constituent element redeposition distances.