Journal
IEEE TRANSACTIONS ON PLASMA SCIENCE
Volume 42, Issue 4, Pages 1021-1025Publisher
IEEE-INST ELECTRICAL ELECTRONICS ENGINEERS INC
DOI: 10.1109/TPS.2014.2307581
Keywords
Chinese Fusion Engineering Test Reactor (CFETR); divertor; equilibria; snowflake
Categories
Funding
- Major State Basic Research Development Program of China (973 Program) [2012GB105000]
- National Magnetic Confinement Fusion Science Program [2011GB114000]
- Key Project of Knowledge Innovation Program of Chinese Academy of Sciences [KJCX3.SYW.N4]
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The Chinese Fusion Engineering Test Reactor (CFETR) is under conceptual design, which will complement ITER. One of the critical issues for the long pulse or steady-state operation in CFETR is how to reduce heat loads below a limit on plasma facing components, especially on divertor plates. This paper presents the selected optimized results of the snowflake diverted equilibria in CFETR.
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