3D thermal-hydraulic analysis of two irregular field joints for the ITER vacuum vessel

被引:2
|
作者
Savoldi, Laura [1 ]
Bonifetto, Roberto [1 ]
Izquierdo, Jesus [2 ]
Le Barbier, Robin [3 ]
Utin, Yuri [3 ]
Zanino, Roberto [1 ]
机构
[1] Politecn Torino, Dipartimento Energia, I-10129 Turin, Italy
[2] Fus Energy, ES-08019 Barcelona, Spain
[3] ITER Org, F-13067 St Paul Les Durance, France
关键词
Nuclear fusion; ITER; Vacuum vessel; Thermal-hydraulics; CFD; SECTOR; DESIGN;
D O I
10.1016/j.fusengdes.2015.06.038
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
In ITER, so-called "Irregular" Field Joints (IFJs) are foreseen at the interface between irregular sectors of the Vacuum Vessel (VV), which is located inside the cryostat and houses the in-vessel components. In the IFIs, a peculiar design of the equatorial port, with respect to that adopted in the Regular Field Joints (RFIs), accommodates the irregularities of the adjacent VV sectors. The IFJs are subject to nuclear heating and actively cooled by sub-cooled pressurized water flowing in a dedicated hydraulic loop, which includes the space left open by the borated In-Wall Shielding (IWS). Here we perform the 3D steady state thermal-hydraulic analysis of two different IFIs using the Computational Fluid Dynamics (CFD) software ANSYS-FLUENT (R). The water flow field, the pressure drop and the temperature maps are computed. The thermal performance of the IFJs in nominal operation is compared to that of an RFJ and it is shown that also in this case enough cooling capability is available to avoid hot spots above the design limits, while the pressure drop remains acceptably low. (C) 2015 Elsevier B.V. All rights reserved.
引用
收藏
页码:1605 / 1609
页数:5
相关论文
共 50 条
  • [1] 3D thermal-hydraulic analysis of an ITER vacuum vessel regular Field Joint
    Richard, L. Savoldi
    Bonifetto, R.
    Corpino, S.
    Izquierdo, J.
    Le Barbier, R.
    Utin, Yu.
    Zanino, R.
    [J]. FUSION ENGINEERING AND DESIGN, 2014, 89 (7-8) : 1848 - 1853
  • [2] Thermal-hydraulic analysis of an irregular sector of the ITER vacuum vessel by means of CFD tools
    Fradera, J.
    Colomer, C.
    Fabbri, M.
    Martin, M.
    Martinez-Saban, E.
    Zamora, I.
    Aleman, A.
    Izquierdo, J.
    Le Barbier, R.
    Utin, Y.
    [J]. FUSION ENGINEERING AND DESIGN, 2015, 92 : 69 - 74
  • [3] CFD analysis of a regular sector of the ITER vacuum vessel. Part II: Thermal-hydraulic effects of the nuclear heat load
    Zanino, R.
    Richard, L. Savoldi
    Subba, F.
    Corpino, S.
    Izquierdo, J.
    Le Barbier, R.
    Utin, Y.
    [J]. FUSION ENGINEERING AND DESIGN, 2013, 88 (12) : 3248 - 3262
  • [4] Thermal and hydraulic assessments of the cooling system for ITER vacuum vessel
    Hosokai, I
    Ikeda, T
    Shibui, M
    Yanagi, Y
    Koizumi, K
    Itou, Y
    Ohmori, J
    Nakahira, M
    Tada, E
    Johnson, G
    [J]. 17TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, VOLS 1 AND 2, 1998, : 1017 - 1020
  • [5] Thermal-hydraulic evaluation of 3D printed microstructures
    Trevizoli, P., V
    Teyber, R.
    da Silveira, P. S.
    Scharf, F.
    Schillo, S. M.
    Niknia, I
    Govindappa, P.
    Christiaanse, T., V
    Rowe, A.
    [J]. APPLIED THERMAL ENGINEERING, 2019, 160
  • [6] Computationally efficient methodology of 3D thermal-hydraulic analysis of Diagnostic Shielding Module #2 of ITER Equatorial Port #11
    Pozhilov, A.
    Guirao, J.
    Udintsev, V.
    Lobachev, A.
    Smirnov, A.
    Modestov, V.
    Ivantsivskiy, M.
    Sulyaev, Y.
    [J]. FUSION ENGINEERING AND DESIGN, 2023, 192
  • [7] Thermal-hydraulic issues in the ITER Toroidal Field Model Coil (TFMC) test and analysis
    Zanino, R
    Bagnasco, M
    Fillunger, H
    Heller, R
    Richard, LS
    Suesser, M
    Zahn, G
    [J]. ADVANCES IN CRYOGENIC ENGINEERING, VOLS. 49A AND B, 2004, 710 : 685 - 692
  • [8] Design and thermal/hydraulic characteristics of the ITER-FEAT vacuum vessel
    Onozuka, M
    Ioki, K
    Sannazzaro, G
    Utin, Y
    Yoshimura, H
    [J]. FUSION ENGINEERING AND DESIGN, 2001, 58-59 : 857 - 861
  • [9] Thermal-hydraulic analysis of the cool-down for the ITER magnets
    Peng, N.
    Liu, L. Q.
    Xiong, L. Y.
    [J]. CRYOGENICS, 2013, 57 : 45 - 49
  • [10] Thermal-hydraulic modelling and analysis of ITER tungsten divertor monoblock
    El-Morshedy, Salah El-Din
    [J]. NUCLEAR MATERIALS AND ENERGY, 2021, 28