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Overview of decade-long development of plasma-facing components at ASIPP

  • G. N. Luo
  • , G. H. Liu
  • , Q. Li
  • , S. G. Qin
  • , W. J. Wang
  • , Y. L. Shi
  • , C. Y. Xie
  • , Z. M. Chen
  • , M. Missirlian
  • , D. Guilhem
  • , M. Richou
  • , T. Hirai
  • , F. Escourbiac
  • , D. M. Yao
  • , J. L. Chen
  • , T. J. Wang
  • , J. Bucalossi
  • , M. Merola
  • , J. G. Li
  • CAS - Institute of Plasma Physics
  • Advanced Technology and Materials Co. Ltd (ATandM)
  • Xi'an Jiaotong University
  • Commissariat à l’énergie atomique et aux énergies alternatives
  • ITER

科研成果: 期刊稿件文献综述同行评审

116 引用 (Scopus)

摘要

The first EAST (Experimental Advanced Superconducting Tokamak) plasma ignited in 2006 with non-actively cooled steel plates as the plasma-facing materials and components (PFMCs) which were then upgraded into full graphite tiles bolted onto water-cooled copper heat sinks in 2008. The first wall was changed further into molybdenum alloy in 2012, while keeping the graphite for both the upper and lower divertors. With the rapid increase in heating and current driving 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 80 cassette bodies toroidally assembled. Commissioning of the EAST upper W/Cu divertor in 2014 was unsatisfactory and then several practical measures were implemented to improve the design, welding quality and reliability, which helped us achieve successful commissioning in the 2015 Spring Campaign. In collaboration with the IO and CEA teams, we have demonstrated our technological capability to remove heat loads of 5000 cycles at 10 MW m-2 and 1000 cycles at 20 MW m-2 for the small scale monoblock mockups, and surprisingly over 300 cycles at 20 MW m-2 for the flat-tile ones. The experience and lessons we learned from batch production and commissioning are undoubtedly valuable for ITER (International Thermonuclear Experimental Reactor) engineering validation and tungsten-related plasma physics.

源语言英语
文章编号065001
期刊Nuclear Fusion
57
6
DOI
出版状态已出版 - 13 4月 2017
已对外发布

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