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
  • [31] ITER prototype divertor cassette design, manufacturing and assembly plans
    Driemeyer, DE
    Cole, FR
    Slattery, KT
    Wille, GW
    17TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, VOLS 1 AND 2, 1998, : 344 - 348
  • [32] Results and analysis of high heat flux tests on a full-scale vertical target prototype of ITER divertor
    Missirlian, M
    Escourbiac, F
    Merola, M
    Bobin-Vastra, I
    Schlosser, J
    Durocher, A
    FUSION ENGINEERING AND DESIGN, 2005, 75-79 : 435 - 440
  • [33] GAS-TARGET AND DETACHED PLASMA REGIMES FOR THE ITER DIVERTOR
    PETRAVIC, M
    STOTLER, DP
    JOURNAL OF NUCLEAR MATERIALS, 1995, 220 : 1097 - 1101
  • [34] Design study of ITER-like divertor target for DEMO
    Crescenzi, Fabio
    Bachmann, C.
    Richou, M.
    Roccella, S.
    Visca, E.
    You, J. -H.
    FUSION ENGINEERING AND DESIGN, 2015, 98-99 : 1263 - 1266
  • [35] FEASIBILITY OF GAS-TARGET MODE OF DIVERTOR OPERATION IN ITER
    KUKUSHKIN, AS
    CONTRIBUTIONS TO PLASMA PHYSICS, 1994, 34 (2-3) : 282 - 292
  • [36] R&D activities on manufacturing plasma-facing unit for prototype of ITER divertor outer target in JADA
    Ezato, Koichiro
    Suzuki, Satoshi
    Seki, Yohji
    Nishi, Hiroshi
    Mohri, Kensuke
    Enoeda, Mikio
    FUSION ENGINEERING AND DESIGN, 2012, 87 (7-8) : 1177 - 1180
  • [37] Laser welding of plasma facing units for ITER divertor Dome manufacturing
    Mazaev, S.
    Gurieva, T.
    Lapin, A.
    Makhankov, A.
    Mirgorodsky, V.
    Natochev, S.
    Nomokonova, O.
    Vlasov, I.
    Ignatov, A.
    2011 IEEE/NPSS 24TH SYMPOSIUM ON FUSION ENGINEERING (SOFE), 2011,
  • [38] Manufacturing and testing of a HETS module for DEMO divertor
    Visca, Eliseo
    Agostini, Pietro
    Crescenzi, Fabio
    Malavasi, A.
    Pizzuto, Aldo
    Rossi, Paolo
    Storai, Sandro
    Utili, Marco
    FUSION ENGINEERING AND DESIGN, 2012, 87 (7-8) : 941 - 945
  • [39] 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
  • [40] THE ITER DIVERTOR CONCEPT
    JANESCHITZ, G
    BORRASS, K
    FEDERICI, G
    IGITKHANOV, Y
    KUKUSHKIN, A
    PACHER, HD
    PACHER, GW
    SUGIHARA, M
    JOURNAL OF NUCLEAR MATERIALS, 1995, 220 : 73 - 88