Plasma facing components for the Experimental Advanced Superconducting Tokamak and CFETR

Three generations of plasma facing components (PFCs) have been used in Experimental Advanced Superconducting Tokamak (EAST): stainless steel for the initial campaign, fully actively cooled doped graphite PFC and a combination of a graphite divertor with a molybdenum first wall. The doped graphite with a ∼100 μm-thick SiC coating has shown good performance for the past 5 years with a heat load removal capacity of 2 MW m−2. An ITER-like W mono-block divertor and W flat-type tiles will be used in the second phase of EAST with long pulse operation beginning in 2013. A hot W wall over 350 °C will be used in the third phase of EAST operation from 2017 when nearly 40 MW of heating and current drive power will be utilized. Combining these experiences of PFCs together with divertor operation optimization, a solid technical basis will be established for the Chinese Fusion Engineering Testing Reactor.

[1]  L. Zakharov,et al.  Lithium coating for H-mode and high performance plasmas on EAST in ASIPP , 2013 .

[2]  Jiafeng Chang,et al.  Improvement of divertor triple probe system and its measurements under full graphite wall on EAST , 2009 .

[3]  Lei Zhang,et al.  The primary results for the mixed carbon material used for high flux steady-state tokamak operation in China , 2001 .

[4]  Q. Guo,et al.  Coating materials for fusion application in China , 2011 .

[5]  Eliseo Visca,et al.  Pre-brazed casting and hot radial pressing: A reliable process for the manufacturing of CFC and W monoblock mock-ups , 2007 .

[6]  Q. Hu,et al.  The first in-vessel cryopump for EAST divertor experiment , 2010 .

[7]  F. Gao,et al.  Limiter material experiments towards long pulse operation in the HT-7 superconducting tokamak , 2007 .

[8]  J. Li,et al.  Development of Carbon Based Plasma Facing Components for Steady State Operation of the Fusion Devices in China , 2004 .

[9]  Jiefeng Wu,et al.  Plasma facing components of EAST , 2010 .

[10]  Li Wang,et al.  Vacuum and wall conditioning system on EAST , 2009 .

[11]  J. Chen,et al.  Overview of R&D on Plasma-Facing Materials and Components in China , 2012 .

[12]  M. Merola,et al.  Testing of high heat flux components manufactured by ENEA for ITER divertor , 2009 .

[13]  J. Li,et al.  Overview of plasma-facing materials and components for EAST , 2007 .

[14]  Yixue Chen,et al.  Recent progress on divertor operations in EAST , 2011 .

[15]  R. H. Bulmer,et al.  Sustained Spheromak Physics Experiment (SSPX): design and physics results , 2012 .