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PPCA2-I - Fusion Reactor Related Technologies Development in ASIPP
Songtao Wu, Qunying Huang, Junling Chen, Yican Wu
Institute of Plasma Physics, Chinese Academy of Sciences
Abstract: Fusion research in the world has nowadays been focused on the R&D of future fusion reactor
technologies, such as technologies of large scale superconducting magnets, RF/NBI heating and current drive,
blanket and divertor, plasma control and diagnostics, tritium recycling and radiation resistant materials. Some
key technologies have been developed by the projects of HT-7 in operation and EAST being built in the Institute
of Plasma Physics, Chinese Academy of Sciences (ASIPP). The technologies, such as long pulse discharges for
plasma initiation with low loop voltage, wall conditioning, plasma facing material (PFM), non-inductive current
drive and heating, plasma control and data acquisition and processing etc., have been developed very well on the
HT-7 superconducting tokamak in the past five years. The R&D programs of EAST have been quite successful,
which have been especially focusing on the superconducting technologies development, such as design,
fabrication and test technologies of large scale magnets and cable-in-conduit conductor. A multi-element doped
graphite and thick gradient SiC coatings on carbon based materials (CBM) have been developed as plasma
facing materials of the EAST device. Detailed investigation of the composition has been done. High-Z materials,
e.g. Mo and W, and functionally graded materials for PFM have also been studied in China. As a primary
candidate of structural materials of blanket, the Chinese version of the RAFM (Reduced Activation
Ferritic/Marntensitic) steels, e.g. CLAM (China Low Activation Ferritic-Martensitic) steel, are being developed
in ASIPP. In this paper, some key technologies developed in ASIPP are introduced.
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Synopsis (pdf)