High heat flux test of SiC coated doped graphite

被引:8
作者
Guo, Q. G.
Liu, Zh. J.
Li, J. G.
Noda, N.
Kubota, Y.
Liu, L.
机构
[1] Chinese Acad Sci, Inst Coal Chem, Key Lab Carbon Mat, Shanxi 030001, Peoples R China
[2] Chinese Acad Sci, Inst Plasma Phys, Hefei, Peoples R China
[3] Natl Inst Fus Sci, Toki 5095292, Japan
关键词
doped graphite; coating; electron beam heating; heat flux;
D O I
10.1016/j.jnucmat.2007.01.250
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Doped graphites containing B, Si and Ti dopants with improved mechanical and thermal properties are developed as divertor plates in experimental advanced superconducting tokamak (EAST) device. SiC coatings with a grading distribution along the depth up to 100 pm from the surface were applied on the doped graphites by chemical vapor reaction (CVR) method in order to reduce the carbon impurities emitted from the surface of doped graphites during long pulse plasma discharge. High heat flux test on SiC coated graphites were carried out with an active cooling test (ACT) facility. Results show that SiC coated doped graphites can handle heat flux up to 6 MW/m(2) while keeping structural integrity. The abrupt increase of surface temperature and the eroded pot on the surface implied that SiC coatings acted as a heat transfer barrier when irradiated with heat flux of 6 MW/m(2) (c) 2007 Elsevier B.V. All rights reserved.
引用
收藏
页码:1216 / 1220
页数:5
相关论文
共 9 条
  • [1] Development of carbon based plasma facing components for steady state operation of the fusion devices in China
    Chen, J. L.
    Li, J. G.
    Li, H.
    Guo, Q. G.
    [J]. PHYSICA SCRIPTA, 2004, T111 : 173 - 180
  • [2] Selection of candidate doped graphite materials as plasma facing components for HT-7U device
    Guo, QG
    Li, JG
    Noda, N
    Kubota, Y
    Chen, JL
    Liu, ZJ
    Liu, L
    Song, JR
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2003, 313 : 144 - 148
  • [3] Oxidation protection of graphite and B4C-modified graphite by a SiC coating
    Guo, QG
    Song, JR
    Liu, L
    Zhang, BJ
    [J]. CARBON, 1999, 37 (01) : 149 - 152
  • [4] The primary results for the mixed carbon material used for high flux steady-state tokamak operation in China
    Guo, QG
    Li, JG
    Zhai, GT
    Liu, L
    Song, JR
    Zhang, LF
    He, YX
    Chen, JL
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2001, 290 : 191 - 195
  • [5] Primary results of the upgraded actively cooled limiter system of HT-7
    Hu, JS
    Li, JG
    Zhang, XD
    Luo, NC
    Li, H
    [J]. FUSION ENGINEERING AND DESIGN, 2005, 73 (2-4) : 119 - 125
  • [6] Design of actively cooled flat toroidal limiter with CuCr heat sink for the HT-7 superconducting tokamak
    Hu, JS
    Li, JG
    Zhang, XD
    Luo, NC
    Li, H
    [J]. FUSION ENGINEERING AND DESIGN, 2005, 72 (04) : 377 - 390
  • [7] Developments and high heat flux tests of divertor components for LHD
    Kubota, Y
    Noda, N
    Sagara, A
    Sakamoto, R
    Motojima, O
    Fujita, I
    Hino, T
    Yamashina, T
    Tokunaga, K
    Yoshida, N
    [J]. FUSION ENGINEERING AND DESIGN, 1998, 39-40 : 247 - 252
  • [8] Structural analysis and manufacture for the vacuum vessel of experimental advanced superconducting tokamak (EAST) device
    Song, YT
    Yao, DA
    Wu, S
    Weng, P
    [J]. FUSION ENGINEERING AND DESIGN, 2006, 81 (8-14) : 1117 - 1122
  • [9] EAST in-vessel components design
    Yao, DM
    Li, JG
    Song, YT
    Du, SJ
    Chen, JL
    Weng, PD
    [J]. FUSION ENGINEERING AND DESIGN, 2005, 75-79 : 491 - 494