Calculations of pressure drop and mass flow distribution in the toroidal field model coil of the ITER project

被引:28
|
作者
Nicollet, S [1 ]
Duchateau, JL
Fillunger, H
Martinez, A
机构
[1] CEA Cadarache, CEA, EURATOM Assoc, Dept Rech Fus Controlee, F-13108 St Paul Durance, France
[2] EFDA, D-85748 Garching, Germany
关键词
cable-in-conduit conductors; forced flow; fusion magnets;
D O I
10.1016/S0011-2275(01)00014-5
中图分类号
O414.1 [热力学];
学科分类号
摘要
In preparation of the ITER FEAT project, a superconducting toroidal field model coil (TFMC) including 10 parallel pancakes of between 72.2 and 82.0 m long cable-in-conduit conductor (CICC) has been built and has to be tested at FZK. A series of preliminary tests were performed at room temperature and in nitrogen at both CEA-Cadarache and Ansaldo. The tests aimed to assess the thermohydraulics of this coil and specifically to address the pressure drop and the friction factor of the dual channel CICC in a range of Reynolds numbers relevant to the TFMC. These measurements are compared with the predictions which include a hydraulic description of the joint region whose contribution to the total pressure drop is non-negligible. The mass flow distribution between the bundle region and the central channel will be calculated for the cable as well as for the joint region. Measurements on the central solenoid model coil (first layer of inner module and insert coil) in normal operating conditions with supercritical helium are presented. They are in good agreement with the calculations performed from the previously validated correlations. A description of the mass flow imbalance between the TFMC pancakes at low temperatures in helium is done. The major influence of the central spiral is confirmed, since two types of spirals have been included in the TFMC pancakes. This distribution varies as a function of the total mass flow of the analysed hydraulic circuits (TF and CS) of ITER-FEAT. (C) 2001 Elsevier Science Ltd. Al rights reserved.
引用
收藏
页码:569 / 575
页数:7
相关论文
共 50 条
  • [1] The ITER toroidal field model coil project
    Ulbricht, A
    Duchateau, JL
    Fietz, WH
    Ciazynski, D
    Fillunger, H
    Fink, S
    Heller, R
    Maix, R
    Nicollet, S
    Raff, S
    Ricci, M
    Salpietro, E
    Zahn, G
    Zanino, R
    Bagnasco, M
    Besette, D
    Bobrov, E
    Bonicelli, T
    Bruzzone, P
    Darweschsad, MS
    Decool, P
    Dolgetta, N
    della Corte, A
    Formisano, A
    Grünhagen, A
    Hertout, P
    Herz, W
    Huguet, M
    Hurd, F
    Ilyin, Y
    Komarek, P
    Libeyre, P
    Marchese, V
    Marinucci, C
    Martinez, A
    Martone, R
    Martovetsky, N
    Michael, P
    Mitchell, N
    Nijhuis, A
    Nöther, G
    Nunoya, Y
    Polak, M
    Portone, A
    Richard, LS
    Spadoni, M
    Süsser, M
    Turtú, S
    Vostner, A
    Takahashi, Y
    FUSION ENGINEERING AND DESIGN, 2005, 73 (2-4) : 189 - 327
  • [2] A Toroidal Field Model Coil for the ITER-FEAT project
    Salpietro, E
    IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2002, 12 (01) : 623 - 628
  • [3] Completion of the ITER toroidal field model coil
    Maix, RK
    Fillunger, H
    Hurd, F
    Salpietro, E
    Mitchell, N
    Libeyre, P
    Decool, P
    Ulbricht, A
    Zahn, G
    Della Corte, A
    Ricci, M
    Bresson, D
    Bourquard, A
    Baudet, F
    Schellong, B
    Theisen, E
    Valle, N
    FUSION ENGINEERING AND DESIGN, 2001, 58-59 : 159 - 164
  • [4] The ITER toroidal field model coil (TFMC)
    Salpietro, E
    Maix, R
    Bevilacqua, G
    Di Bartolo, G
    Fillunger, H
    Mitchell, N
    Turck, B
    Libeyre, P
    Ulbricht, A
    Spadoni, M
    Della Corte, A
    Bieder, H
    Bresson, D
    Krischel, D
    Tardivelli, GE
    FUSION ENGINEERING AND DESIGN, 1999, 46 (2-4) : 151 - 158
  • [5] Flow balancing orifice for ITER toroidal field coil
    Litvinovich, A. V.
    Rodin, I. Y.
    Kovalchuk, O. A.
    Safonov, A. V.
    Stepanov, D. B.
    Guryeva, T. M.
    ADVANCES IN CRYOGENIC ENGINEERING, 2017, 278
  • [6] Manufacture and assembly of the ITER Toroidal Field Model Coil
    Beaudet, F
    Bourquard, A
    Krischel, D
    Maix, R
    Salpeitro, E
    Theisen, E
    Valle, N
    ATW-INTERNATIONALE ZEITSCHRIFT FUR KERNENERGIE, 2001, 46 (11): : 699 - +
  • [7] Mechanical tests of the ITER toroidal field model coil
    Libeyre, P
    Dolgetta, N
    Decool, P
    Raff, S
    Schanz, P
    Wuechner, F
    Fillunger, H
    IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2004, 14 (02) : 1382 - 1387
  • [8] Toroidal field model coil programme for the ITER tokamak
    Salpietro, E
    Maix, RK
    Bevilacqua, G
    Mitchell, N
    Turck, B
    Libeyre, P
    Ulbricht, A
    Zahn, G
    Spadoni, M
    Della Corte, A
    FUSION ENERGY 1996, VOL 2, 1997, : 879 - 887
  • [9] Iter toroidal field model coil (TFMC) design and construction
    Salpietro, E
    FUSION TECHNOLOGY, 1998, 34 (03): : 797 - 801
  • [10] Manufacture, assembly and QA of the ITER toroidal field model coil
    Maix, R
    Fillunger, H
    Hurd, F
    Palmer, J
    Salpietro, E
    Mitchell, N
    Decool, P
    Libeyre, P
    Ulbricht, A
    Zahn, G
    Della Corte, A
    Garré, R
    Schellong, B
    Laurenti, A
    Valle, N
    Bourquard, A
    Bresson, D
    Theisen, E
    IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2000, 10 (01) : 584 - 587