Bulletin of the American Physical Society
60th Annual Meeting of the APS Division of Plasma Physics
Volume 63, Number 11
Monday–Friday, November 5–9, 2018; Portland, Oregon
Session CP11: Poster Session II: Basic Plasma Physics; Boundary, PMI, Proto-MPEX; International Tokamaks; Turbulence and Transport; Other Configurations; Z-pinch, Dense Plasma Focus and MagLIF (2:00pm-5:00pm)
Monday, November 5, 2018
OCC
Room: Exhibit Hall A1&A
Abstract ID: BAPS.2018.DPP.CP11.111
Abstract: CP11.00111 : Progress of Concept Design for CFETR diagnostic system*
Abstract 
Presenter:
Gongshun Li
(Advanced Energy Research Center, Shenzhen University, Shenzhen 518060, People’s Republic of China, Key Laboratory of Optoelectronic Devices and Systems of Ministry of Educati)
Authors:
Gongshun Li
(Advanced Energy Research Center, Shenzhen University, Shenzhen 518060, People’s Republic of China, Key Laboratory of Optoelectronic Devices and Systems of Ministry of Educati)
Xiang Gao
(Institute of Plasma Physics, Chinese Academy of Science, Hefei, Anhui, 230031, P.R. China, Advanced Energy Research Center, Shenzhen University, Shenzhen 518060, People’s Rep)
Yao Yang
(Institute of Plasma Physics, Chinese Academy of Science, Hefei, Anhui, 230031, P.R. China)
Qingsheng Hu
(Institute of Plasma Physics, Chinese Academy of Science, Hefei, Anhui, 230031, P.R. China)
Xiaodong Lin
(Advanced Energy Research Center, Shenzhen University, Shenzhen 518060, People’s Republic of China)
Guoqiang Li
(Institute of Plasma Physics, Chinese Academy of Science, Hefei, Anhui, 230031, P.R. China)
Yumin Wang
(Institute of Plasma Physics, Chinese Academy of Science, Hefei, Anhui, 230031, P.R. China)
Tingfeng Ming
(Institute of Plasma Physics, Chinese Academy of Science, Hefei, Anhui, 230031, P.R. China)
Shaocheng Liu
(Institute of Plasma Physics, Chinese Academy of Science, Hefei, Anhui, 230031, P.R. China)
Erhui Wang
(Institute of Plasma Physics, Chinese Academy of Science, Hefei, Anhui, 230031, P.R. China)
Xiang Han
(Institute of Plasma Physics, Chinese Academy of Science, Hefei, Anhui, 230031, P.R. China)
Chinese Fusion Engineering Test Reactor (CFETR), as the next superconducting tokamak device in the roadmap for the realization of fusion energy in China, aims at bridging the gaps between ITER and DEMO, and has started an integration engineering R&D project since December 2017. This paper will presents current progress of CFETR diagnostic design, which mainly includes three sections: 1) constraints in CFETR environment for diagnostic system, such as high level of neutron flux and influence; 2) one set of candidate measurements and corresponding techniques, which was proposed for CFETR phase I based on ITER’s experience; 3) current status on diagnostic port plug design, such as electromagnetic performance, nuclear shielding, thermal load, remote handling maintenance, etc.
*This work was supported by the Key R&D Program of China (No.2014GB106000）and the National Natural Science Foundation of China (Nos. 11505221, 11675211 and 11605235).
To cite this abstract, use the following reference: http://meetings.aps.org/link/BAPS.2018.DPP.CP11.111
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