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AbstractAbstract
[en] Heat and particle loads on the plasma-facing components are among the most challenging points to be solved for ITER and a reactor design. Alternative magnetic configuration, such as the X-divertor, Super X-divertor and Snowflake divertor may enable tokamak operation at lower peak heat load than a standard Single Null divertor. This paper reports on the modelling of the variations of the second null point present in the advanced magnetic divertor, here so-called quasi-Snowflake configuration, and first experiments performed on the EAST tokamak in 2014. (author)
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Hu Liqun (ed.) (Institute of Plasma Physics, Chinese Academy of Sciences, Hefei (China)); Morita, Shigeru (ed.) (National Institute for Fusion Science, Toki, Gifu (Japan)); Oh, Yeong-Kook (ed.) (National Fusion Research Institute, Daejeon (Korea, Republic of)); National Institute for Fusion Science, Toki, Gifu (Japan); 277 p; Dec 2015; p. 107-114; A3 foresight program seminar on critical physics issues specific to steady state sustainment of high-performance plasmas 2015 China; Nanning (China); 6-9 Jan 2015; 18 refs., 6 figs., 2 tabs.
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Conference
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