Since 18 of December 2019 conferences.iaea.org uses Nucleus credentials. Visit our help pages for information on how to Register and Sign-in using Nucleus.

17–22 Oct 2016
Kyoto International Conference Center
Japan timezone

Overview on Decade Development of Plasma-Facing Components at ASIPP

21 Oct 2016, 08:30
4h
Kyoto International Conference Center

Kyoto International Conference Center

Takaragaike, Sakyo-ku, Kyoto 606-0001 Japan
Poster MPT - Materials Physics and Technology Poster EX/9, EX/10, TH/7, TH/8, IFE/1, MPT/1, FNS/1

Speaker

Prof. G. -N. Luo (CnIPPCAS)

Description

The first EAST plasma was ignited in 2006 with non-actively-cooled steel plates as plasma-facing materials and components (PFMC) which was then upgraded into full graphite tiles bolted onto water-cooled copper heat sinks in 2008. And the first wall was changed further into TZM in 2012, while keeping graphite for both of the upper and lower divertors. With rapid increase in H&CD power in EAST, the W/Cu divertor project was launched around the end of 2012, aiming at achieving actively-cooled full W/Cu-PFCs for the upper divertor, with heat removal capability up to 10 MW/m^2. The W/Cu upper divertor was finished in the spring of 2014, consisting of about 15000 W monoblocks for 160 vertical targets, and 24000 W flat tiles for 160 baffles and 80 domes, on 80 cassette bodies toroidally assembled. Two different types of W/Cu actively-cooled PFCs for the project have been developed at ASIPP. The monoblock PFCs for vertical targets are manufactured by hot isostatic pressing (HIP) for cladding oxygen free Cu (OFC) to the inner surface of the W monoblocks, and then HIPing for the bonding between the clad monoblocks and CuCrZr cooling tube. The flat-tile PFCs for baffles and domes are manufactured by casting OFC onto the rear side of W tiles firstly, followed by HIPing of the W/OFC tiles onto CuCrZr heat sink plate. The non-destructive testing (NDT) quality control system has been established. In collaboration with IO and CEA teams, we have demonstrated our technology capability to remove heat loads of 5000 cycles at 10MW/m^2 and 1000 cycles at 20MW/m^2 for the small scale monoblock mockups, and surprisingly over 300 cycles at 20MW/m^2 for the flat-tile ones. Commissioning of the EAST upper W/Cu divertor in 2014 failed due mainly to leaks of e-beam welding between cooling tube and manifold box. After the campaign, we examined the leaking PFCs and reviewed the whole process, and then implemented several practical measures to improve connection design, component welding quality and installation welding reliability, which helped us achieve successful commissioning in 2015 campaigns. Key technologies being developed at ASIPP for manufacturing W/Cu-PFCs have shown great performance against HHF testing. The experience and lessons we learned for batch production and commissioning are undoubtedly valuable for ITER engineering validation and tungsten-related plasma physics.
Country or International Organization People’s Republic of China
Paper Number MPT/1-2Ra

Primary author

Prof. G. -N. Luo (CnIPPCAS)

Co-authors

Mr C. Y. Xie (CnIPPCAS) Dr D. Guilhem (FrCEA) Prof. D. M. Yao (CnIPPCAS) Mr F. Escourbiac (ITERFr) Mr G. H. Liu (CnATMC) Dr J. Bucalossi (FrCEA) Prof. J. G. Li (CnIPPCAS) Prof. J. L. Chen (CnIPPCAS) Dr M. Merola (ITERFr) Dr M. Missirlian (FrCEA) Dr M. Richou (FrCEA) Dr Q. Li (CnIPPCAS) Mr S. G. Qin (CnATMC) Dr T. Hirai (ITERFr) Mr T. J. Wang (CnATMC) Dr W. J. Wang (CnIPPCAS) Mr Y. L. Shi (CnATMC) Prof. Z. M. Chen (Xi’an Jiaotong University, Xi'an, Shanxi, China)

Presentation materials