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Reduction of hydrogen content in deuterium plasma with mixed graphite and tungsten divertors in EAST

文献类型：期刊论文

作者Zuo, G. Z.3; Hu, J. S.3,4; Yu, Y. W.3; Sun, Z.3; Maingi, R.2; Zhuang, H. D.3; Meng, X. C.1,3; Xu, W.3; Mansfield, D. K.1; Tritz, K.5
刊名FUSION ENGINEERING AND DESIGN
出版日期2018-06-01
卷号131页码:41-48
关键词Hydrogen content Wall temperature Lithium Graphite divertor Tungsten divertor EAST
ISSN号0920-3796
DOI10.1016/j.fusengdes.2018.03.065
通讯作者Hu, J. S.(hujs@ipp.ac.cn)
英文摘要Reduction of hydrogen content in deuterium-fueled fusion plasmas is important not only to avoid diluting reacting core deuterons but also so as to allow the optimization of hydrogen-minority-heating efficiency in those fusion devices which employ ion-cyclotron-radio-frequency heating systems. In EAST, the amount of hydrogen released from plasma-facing components has been shown to depend strongly on both their composition and their temperature. As measured by thermal desorption spectroscopy, the hydrogen inventory in graphite-used in EAST as lower divertor material-has been determined to be > 25 times larger than that of tungsten which comprises the upper divertor. This difference in hydrogen inventory is attributed mostly to the intrinsically porous nature of bulk graphite. Thus the main source of hydrogen release into EAST discharges was identified as the graphite tiles used in the lower divertor. The hydrogen content in EAST plasmas were clearly reduced by first employing a high-temperature vacuum baking of all graphite tiles and then renewing a 100-200 mu m thick SiC coating before an EAST experimental run campaign. Subsequent active surface conditioning of all wall components with elemental silicon and then with elemental lithium were seem to again reduce the plasma hydrogen content significantly-with lithium proving to be more effective than silicon. Combining these several techniques, H/(H + D) levels as low as similar to 3% have been achieved in EAST discharges. Additionally, the effects of lithium thickness on H surface implantation and retention has been re-examined semi-quantitatively using data from a previous run campaign. These data suggest that relatively thick Li films coated on the first wall can effectively isolate the rich source of hydrogen stored in the porous bulk of the underlying graphite from the deuterium-fueled plasma so as to minimize hydrogen release. Finally an operational maneuver whereby a diverted plasma is repetitively switched from an upper single null configuration to a lower single null configuration is presented. This switching maneuver has been shown to suppress hydrogen influx into a 35s-long EAST discharge by alternately mitigating the rise in divertor temperature.
WOS关键词FUSION DEVICES ; PERFORMANCE ; RETENTION ; TOKAMAK ; EDGE
资助项目National Key Research and Development Program of China[2017YFA0402500] ; National Nature Science Foundation of China[11775261] ; National Nature Science Foundation of China[11625524] ; National Nature Science Foundation of China[11605246] ; National Nature Science Foundation of China[11075185] ; National Nature Science Foundation of China[11021565] ; US Department of Energy[DE-AC02-09CH11466]
WOS研究方向Nuclear Science & Technology
语种英语
WOS记录号WOS:000435052400007
出版者ELSEVIER SCIENCE SA
资助机构National Key Research and Development Program of China ; National Key Research and Development Program of China ; National Key Research and Development Program of China ; National Key Research and Development Program of China ; National Key Research and Development Program of China ; National Key Research and Development Program of China ; National Key Research and Development Program of China ; National Key Research and Development Program of China ; National Key Research and Development Program of China ; National Key Research and Development Program of China ; National Key Research and Development Program of China ; National Key Research and Development Program of China ; National Key Research and Development Program of China ; National Key Research and Development Program of China ; National Key Research and Development Program of China ; National Key Research and Development Program of China ; National Key Research and Development Program of China ; National Key Research and Development Program of China ; 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源URL[http://ir.hfcas.ac.cn:8080/handle/334002/38243]  
专题合肥物质科学研究院_中科院等离子体物理研究所
通讯作者Hu, J. S.
作者单位1.Princeton Univ, Plasma Phys Lab, Princeton, NJ 08543 USA
2.Hunan Univ, Dept Appl Phys, Changsha 410082, Hunan, Peoples R China
3.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China
4.CAS Key Lab Photovolta & Energy Conservat Mat, Hefei 230031, Anhui, Peoples R China
5.Johns Hopkins Univ, Baltimore, MD 21211 USA
推荐引用方式
GB/T 7714		 Zuo, G. Z.,Hu, J. S.,Yu, Y. W.,et al. Reduction of hydrogen content in deuterium plasma with mixed graphite and tungsten divertors in EAST[J]. FUSION ENGINEERING AND DESIGN,2018,131:41-48.
APA Zuo, G. Z..,Hu, J. S..,Yu, Y. W..,Sun, Z..,Maingi, R..,...&Li, J. G..(2018).Reduction of hydrogen content in deuterium plasma with mixed graphite and tungsten divertors in EAST.FUSION ENGINEERING AND DESIGN,131,41-48.
MLA Zuo, G. Z.,et al."Reduction of hydrogen content in deuterium plasma with mixed graphite and tungsten divertors in EAST".FUSION ENGINEERING AND DESIGN 131(2018):41-48.

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来源：合肥物质科学研究院

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