ITER DIVERTOR SYSTEM INTEGRATION

被引:0
|
作者
Martin, A. [1 ]
Andrew, P. [1 ]
Jokinen, T. [1 ]
Komarov, V. [1 ]
Kukushkin, A. [1 ]
Loarte, A. [1 ]
Maruyama, S. [1 ]
Merola, M. [1 ]
Palmer, J. [1 ]
Pearce, R. [1 ]
Pick, M. [1 ]
Pitts, R. [1 ]
Walker, C. [1 ]
机构
[1] ITER Org, F-13108 St Paul Les Durance, France
关键词
D O I
10.13182/FST09-A8877
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The main function of the ITER divertor system is to exhaust the major part of the alpha particle power as well as helium and impurities from the plasma. In order to fulfil these functions a divertor, a cooling system, a high vacuum pumping system, diagnostics and a gas injection system need to be integrated into the lower part of the vacuum vessel and into the divertor level ports. All components need to be assembled/disassembled using RH tools. The integration of all these systems has been undertaken to ensure that the overall functionality of the divertor is preserved, while fulfilling the requirements of each specific system.
引用
收藏
页码:65 / 69
页数:5
相关论文
共 50 条
  • [31] Analyses and structural integrity estimation of the ITER divertor Thomson scattering system
    Kirienko, Ivan
    Buslakov, Igor
    Modestov, Victor
    Murtazin, Ilnar
    Mukhin, Eugene
    Litvinov, Andrey
    Koval, Alexandr
    Samsonov, Dmitry
    Senichenkov, Vasily
    Marinin, Gennady
    Terentyev, Denis
    Andrew, Philip
    [J]. FUSION ENGINEERING AND DESIGN, 2019, 146 : 2624 - 2627
  • [32] Status of the engineering design of the ITER divertor
    Chiocchio, S
    Antipenkov, A
    Federici, G
    Ibbott, C
    Heidl, H
    Jakeman, R
    Janeschitz, G
    Martin, E
    Raffray, R
    Tivey, R
    [J]. 17TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, VOLS 1 AND 2, 1998, : 331 - 336
  • [33] Thomson scattering diagnostics for ITER divertor
    Mukhin, E. E.
    Kukushkin, A. S.
    Tolstyakov, S. Yu
    Kochergin, M. M.
    Semenov, V. V.
    Kurskiev, G. S.
    Razdobarin, A. G.
    Podushnikova, K. A.
    Andrew, P.
    [J]. 14TH INTERNATIONAL SYMPOSIUM ON LASER-AIDED PLASMA DIAGNOSTICS (LAPD14), 2010, 227
  • [34] Characteristics of divertor detachment for ITER conditions
    Kukushkin, A. S.
    Pacher, H. D.
    Pitts, R. A.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2015, 463 : 586 - 590
  • [35] Power balance in the ITER plasma and divertor
    Post, DE
    Braams, B
    Mandrekas, J
    Stacey, W
    Putvinskaya, N
    [J]. CONTRIBUTIONS TO PLASMA PHYSICS, 1996, 36 (2-3) : 240 - 244
  • [36] Development of divertor cassette transporters for ITER
    Takeda, N
    Akou, K
    Kakudate, S
    Takiguchi, Y
    Tada, E
    Burgess, T
    Shibanuma, K
    Haange, R
    [J]. 17TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, VOLS 1 AND 2, 1998, : 925 - 928
  • [37] Radiative divertor modelling for ITER and TPX
    Braams, BJ
    [J]. CONTRIBUTIONS TO PLASMA PHYSICS, 1996, 36 (2-3) : 276 - 281
  • [38] REGIMES WITH RECOMBINING PLASMA IN THE ITER DIVERTOR
    KRASHENINNIKOV, SI
    SIGMAR, D
    SOBOLEVA, TK
    KUKUSHKIN, AB
    BATISCHEV, OV
    SIGOV, YS
    [J]. CONTRIBUTIONS TO PLASMA PHYSICS, 1994, 34 (2-3) : 442 - 447
  • [39] European development of the ITER divertor target
    Vieider, G
    Merola, M
    Bonal, JP
    Chappuis, P
    Duglué, D
    Duwe, R
    Escourbiac, F
    Fèbvre, M
    Giancarli, L
    Grattarola, M
    LeMarois, G
    Pacher, HD
    Pizzuto, A
    Plöchl, L
    Riccardi, B
    Rödig, M
    Schlosser, J
    Smid, I
    Tramier, P
    Wu, CH
    [J]. FUSION ENGINEERING AND DESIGN, 1999, 46 (2-4) : 221 - 228
  • [40] Overview of the engineering design of ITER divertor
    Ibbott, C
    Chiocchio, S
    D'Agata, E
    Federici, G
    Heidl, H
    Janeschitz, G
    Martin, E
    Tivey, R
    [J]. FUSION ENGINEERING AND DESIGN, 2001, 56-57 : 243 - 248