Development of divertor high heat flux components for ITER in JAERI

被引:4
|
作者
Suzuki, S [1 ]
Sato, K [1 ]
Ezato, K [1 ]
Yokoyama, K [1 ]
Dairaku, M [1 ]
Nakamura, K [1 ]
Akiba, M [1 ]
机构
[1] Japan Atom Energy Res Inst, NBI Heating Lab, Naka, Ibaraki 3110193, Japan
来源
PHYSICA SCRIPTA | 1999年 / T81卷
关键词
D O I
10.1238/Physica.Topical.081a00089
中图分类号
O4 [物理学];
学科分类号
0702 ;
摘要
Development of divertor high heat flux components is one of the critical issues to realize next generation fusion experimental reactors, such as ITER. In ITER, the surface heat flux to the divertor is designed to be 5 MW/m(2) in normal operation and 20 MW/m(2) in transient operation. To withstand such high heat fluxes, the plasma-facing surface of the divertor components is covered with refractory armor materials. A carbon-fiber-reinforced carbon composite (CFC) is one of the candidate armor materials for the ITER divertor plate. JAERI has vigorously been developing the divertor high heat flux components with CFC armor materials. High heat flux experiments of various divertor mock-ups were carried out in a high heat flux test facility in JAERI. As a result of a thermal cycling experiment, a small-scale divertor mock-up with 3D-CFC armor tiles could withstand a cyclic heat flux of 20 MW/m(2) for 1000 cycles with no degradation of thermal performance. A silver-free braze technique using Cu-Mn braze material was found to be a promising solution for the ITER divertor application. As a result of thermal cycling experiments of full-scale ITER divertor mock-ups, the mock-ups with 1D-CFC armor tiles could endure a cyclic heat flux of 5 MW/m(2) up to 1000 cycles with no degradation of the braze interface of the 1D-CFC armor tiles. On the other hand, the mock-up with 3D-CFC armor tiles showed detachment of some armor tiles in an early stage of the experiment.
引用
收藏
页码:89 / 93
页数:5
相关论文
共 50 条
  • [31] Divertor development for ITER
    Janeschitz, G
    Ando, T
    Antipenkov, A
    Barabash, V
    Chiocchio, S
    Federici, G
    Ibbott, C
    Jakeman, R
    Matera, R
    Martin, E
    Pacher, HD
    Parker, R
    Tivey, R
    FUSION ENGINEERING AND DESIGN, 1998, 39-40 : 173 - 187
  • [32] Development of continuous V-shaped structure for high heat flux components of flat-type divertor
    Feng, Siqing
    Peng, Xuebing
    Song, Yuntao
    Liu, Peng
    Song, Wei
    Mao, Xin
    Qian, Xinyuan
    Khan, Muhammad Salman
    NUCLEAR MATERIALS AND ENERGY, 2023, 35
  • [33] Fusion technology development for ITER in JAERI
    Seki, M
    Tsuji, H
    Ohara, Y
    Akiba, M
    Okumura, Y
    FUSION TECHNOLOGY, 2001, 39 (02): : 367 - 373
  • [34] The design of the high heat flux components of the ITER neutral beam injection system
    Di Pietro, E
    Inoue, T
    Krylov, A
    Murasaka, E
    Hemsworth, R
    Alexandrov, E
    Barinov, M
    Dlougach, E
    Kulygin, V
    Naumov, V
    Panasenkov, A
    Petrov, V
    Fujiwara, Y
    Ohara, Y
    Okumura, Y
    Tanii, M
    PLASMA DEVICES AND OPERATIONS, 1998, 6 (1-3): : 119 - 127
  • [35] 3D thermal elasto plastic analysis of ITER divertor high heat flux elements
    Bykov, VA
    Komarov, VM
    Mazul, IV
    Borovkov, AI
    Semenov, AS
    PLASMA DEVICES AND OPERATIONS, 1998, 6 (1-3): : 55 - 63
  • [36] The beamline for the ITER heating neutral beam injectors: A case study for development and procurement of high heat flux components
    Dalla Palma, Mauro
    Pasqualotto, Roberto
    Sartori, Emanuele
    Tinti, Paolo
    Zaccaria, Pierluigi
    Zaupa, Matteo
    Krilov, Alexander
    Panasenkov, Alexander
    Blatchford, Peter
    Chuilon, Ben
    Xue, Yong
    Hanke, Stefan
    Guaman, Santiago Ludgardo Ochoa
    Graceffa, Joseph
    Bragulat, Eduard
    Mico Montava, Gonzalo
    Morenog Canamero, Juan Francisco
    FUSION ENGINEERING AND DESIGN, 2021, 171
  • [37] Heat flux depositions on the WEST divertor and first wall components
    Firdaouss, M.
    Batal, T.
    Bucalossi, J.
    Languille, P.
    Nardon, E.
    Richou, M.
    FUSION ENGINEERING AND DESIGN, 2015, 98-99 : 1294 - 1298
  • [38] Overview of the Japanese mock-up tests for ITER high heat flux components
    Akiba, M
    Suzuki, S
    FUSION ENGINEERING AND DESIGN, 1998, 39-40 : 219 - 225
  • [39] Non-destructive methods for the defect detection in the ITER high heat flux components
    Roccella, S.
    Burrasca, G.
    Cacciotti, E.
    Castillo, A.
    Mancini, A.
    Pizzuto, A.
    Tati, A.
    Visca, E.
    FUSION ENGINEERING AND DESIGN, 2011, 86 (9-11) : 1791 - 1796
  • [40] Results of high heat flux tests of tungsten divertor targets under plasma heat loads expected in ITER and tokamaks (review)
    V. P. Budaev
    Physics of Atomic Nuclei, 2016, 79 : 1137 - 1162