Manufacturing and testing of a prototypical divertor vertical target for ITER

被引:23
|
作者
Merola, M
Plöchl, L
Chappuis, P
Escourbiac, F
Grattarola, M
Smid, I
Tivey, R
Vieider, G
机构
[1] EFDA Close Support Unit, D-85748 Garching, Germany
[2] Plansee AG, Reutte, Austria
[3] CEA, Cadarache, France
[4] ATEM, Marseille, France
[5] Ansaldo Ric, Genoa, Italy
[6] Austrian Res Ctr, Seibersdorf, Austria
关键词
D O I
10.1016/S0022-3115(00)00150-1
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
After an extensive R&D activity, a medium-scale divertor vertical target prototype has been manufactured by the EU Home Team. This component contains all the main features of the corresponding ITER divertor design and consists of two units with one cooling channel each, assembled together and having an overall length and width of about 600 and 50 mm, respectively. The upper part of the prototype has a tungsten macro-brush armour, whereas the lower part is covered by CFC monoblocks. A number of joining techniques were required to manufacture this component as well as an appreciable effort in the development of suitable non-destructive testing methods. The component was high heat flux tested in FE200 electron beam facility at Le Creusot, France. Tt endured 100 cycles at 5 MW/m(2), 1000 cycles at 10 MW/m(2) and more then 1000 cycles at 15-20 MW/m(2). The final critical heat Aux test reached a value in excess of 30 MW/m(2). (C) 2000 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:1068 / 1072
页数:5
相关论文
共 50 条
  • [41] Reflectometry in the ITER divertor
    Manso, M
    Cupido, L
    Leclert, G
    Wagner, D
    Vayakis, G
    Donne, A
    de Kock, L
    Laviron, C
    Sanchez, J
    Serra, F
    Silva, A
    Walker, C
    DIAGNOSTICS FOR EXPERIMENTAL THERMONUCLEAR FUSION REACTORS 2, 1998, : 139 - 150
  • [42] Development of ITER divertor vertical target with annular flow concept - I: Thermal-hydraulic characteristics of annular swirl tube
    Ezato, K
    Dairaku, M
    Taniguchi, M
    Sato, K
    Suzuki, S
    Akiba, M
    Ibbott, C
    Tivey, R
    FUSION SCIENCE AND TECHNOLOGY, 2004, 46 (04) : 521 - 529
  • [43] Testing of high heat flux components manufactured by ENEA for ITER divertor
    Visca, Eliseo
    Escourbiac, F.
    Libera, S.
    Mancini, A.
    Mazzone, G.
    Merola, M.
    Pizzuto, A.
    FUSION ENGINEERING AND DESIGN, 2009, 84 (2-6) : 309 - 313
  • [44] Ion orbit modelling of ELM heat loads on ITER divertor vertical targets
    Gunn, J. P.
    Carpentier-Chouchana, S.
    Dejarnac, R.
    Escourbiac, F.
    Hirai, T.
    Komm, M.
    Kukushkin, A.
    Panayotis, S.
    Pitts, R. A.
    NUCLEAR MATERIALS AND ENERGY, 2017, 12 : 75 - 83
  • [45] Repair of manufacturing defects in the armor of plasma facing units of the ITER Divertor Dome
    Litunovsky, Nikolay
    Alekseenko, Evgeny
    Kuznetsov, Vladimir
    Lyanzberg, Dmitriy
    Makhankov, Aleksey
    Rulev, Roman
    FUSION ENGINEERING AND DESIGN, 2013, 88 (9-10) : 1739 - 1743
  • [46] Equilibrium and vertical-instability considerations for vertical strike-point shifts on the ITER divertor targets
    Kolesnikov, R. A.
    Bulmer, R. H.
    LoDestro, L.
    Casper, T. A.
    Pitts, R. A.
    NUCLEAR FUSION, 2013, 53 (08)
  • [47] Manufacturing and testing of a Be/OFHC-Cu divertor module
    Araki, M
    Youchison, DL
    Akiba, M
    Watson, RD
    Sato, K
    Suzuki, S
    JOURNAL OF NUCLEAR MATERIALS, 1996, 233 : 632 - 637
  • [48] ITER-like divertor target for DEMO: Design study and fabrication test
    Crescenzi, F.
    Greuner, H.
    Roccella, S.
    Visca, E.
    You, J. H.
    FUSION ENGINEERING AND DESIGN, 2017, 124 : 432 - 436
  • [49] Fabrication of monoblock high heat flux components for ITER divertor upper vertical target using hot isostatic pressing diffusion welding
    Rigal, E
    Bucci, P
    Le Marois, G
    FUSION ENGINEERING AND DESIGN, 2000, 49-50 : 317 - 322
  • [50] Numerical simulation of CFC and tungsten target erosion in ITER-FEAT divertor
    Filatov, V
    JOURNAL OF NUCLEAR MATERIALS, 2003, 313 : 393 - 398