Progress status of the ITER Vacuum Vessel sectors manufacturing design thermal hydraulic performance

被引:1
|
作者
Colomer, C. [1 ]
Briani, P. [1 ]
Fradera, J. [1 ]
Ichard, M. [1 ]
Aleman, A. [1 ]
Martinez-Saban, E. [1 ]
Zamora, I. [1 ]
Hermosa, B. [1 ]
Martin, M. [1 ]
Mata, O. [1 ]
Martell, A. [1 ]
Martinez, J. M. [2 ]
Sabourin, F. [2 ]
Martin, A. [2 ]
Cau, F. [3 ]
Caixas, J. [3 ]
Portone, A. [3 ]
机构
[1] IDOM Consulting Engn Architecture SAU, Gran Via Carles 3 97 Baixos, Barcelona 08028, Spain
[2] ITER Org, Route Vinon Sur Verdon,CS 90046, F-13067 St Paul Les Durance, France
[3] Fus Energy F4E, C Josep Pla,2,Edificio B3, E-08019 Barcelona, Spain
关键词
Nuclear fusion ITER; Vacuum Vessel; Thermal hydraulics; CFD; CHT (Conjugate heat transfer);
D O I
10.1016/j.fusengdes.2017.03.095
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 present work exposes the 3D steady state thermal hydraulic (TH) analysis of the Irregular Sector number 3 (IrS#3) of the ITER Vacuum Vessel (VV), including the Irregular Field Joints (IrFJ) by means of a commercial CFD (Computational Fluid Dynamics) code. The geometry of the IrS#3 has been simplified and healed in order to be suitable for CFD analysis. The simplified geometry has been meshed and converted to a polyhedral cell based mesh so as to enhance accuracy and calculation stability. Nuclear heat deposition (H) from the latest C Lite model [1] has been implemented through several User Defined Functions (UDF). Water coolant and stainless steel shell are solved together as a steady state conjugate heat transfer problem in order to assess the impact of the nuclear heat deposition on the IrS#3 cooling scheme. Hence, the IrS#3 is simulated as a whole, without splitting the domain. Results show the total IrS#3 pressure drop as well as the flow and temperature distribution all over the IrS#3. Moreover, the heat transfer coefficient (h) has been calculated at the fluid-solid interface. Velocity magnitude in the water coolant has an average value of 0.10 m/s and mass flow rate distribution is 11% and 89% respectively for Inboard and Outboard. The pressure drop, mainly concentrated at inlet and outlet ducts, is of 77.4 kPa. The average his of 5.690 W/(m(2)K), way above the design limit of 500 W/(m(2)K). The fluid temperature stays at an average value of 101.7 degrees C. The results obtained have a significant importance regarding design and safety and give a valuable insight on the current cooling scheme and system behavior for the IrS#3 of the ITER W. This follows a previous work presenting the methodology and the results of a 3D TH analysis of the Irregular Sector number 2 (IrS#2) of the ITER Vacuum Vessel (W) by means of CFD [2]. (C) 2017 Elsevier B.V. All rights reserved.
引用
收藏
页码:578 / 581
页数:4
相关论文
共 50 条
  • [1] Design progress of the ITER vacuum vessel sectors and port structures
    Utin, Yu.
    Iokia, K.
    Alekseev, A.
    Bachmann, Ch.
    Cho, S.
    Chuyanov, V.
    Jones, L.
    Kuzmin, E.
    Morimoto, A.
    Nakahira, M.
    Sannazzaro, G.
    [J]. FUSION ENGINEERING AND DESIGN, 2007, 82 (15-24) : 2040 - 2046
  • [2] Challenging issues in the design and manufacturing of the European sectors of the ITER vacuum vessel
    Dans, Andres
    Jucker, P.
    Bayon, A.
    Arbogast, J. -F.
    Caixas, J.
    Fernandez, J.
    Mico, G.
    Pacheco, J.
    Trentea, A.
    Stamos, V.
    [J]. FUSION ENGINEERING AND DESIGN, 2014, 89 (7-8) : 1769 - 1774
  • [3] Design progress of the vacuum vessel sectors and ports towards the ITER construction
    Utin, Yu.
    Loki, K.
    Bachmann, Ch.
    Barabash, V.
    Federici, G.
    Jones, L.
    Kim, B. C.
    Kuzmin, E.
    Morimoto, M.
    Nakahira, M.
    Sannazzaro, G.
    [J]. FUSION ENGINEERING AND DESIGN, 2008, 83 (10-12) : 1565 - 1570
  • [4] Design progress of the Vacuum Vessel for ITER
    Onozuka, M
    Johnson, G
    Ioki, K
    Sannazzaro, G
    Utin, Y
    Takahashi, K
    Iizuka, T
    Parker, R
    Koizumi, K
    Kuzmin, E
    Neilson, H
    Nelson, B
    Vallone, C
    [J]. 17TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, VOLS 1 AND 2, 1998, : 1013 - 1016
  • [5] 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
  • [6] Manufacturing progress of first delivery sector of ITER vacuum vessel thermal shield
    Kang, Dong Kwon
    Nam, Kwanwoo
    Kang, Kyoung-O
    Noh, Chang Hyun
    Chung, Wooho
    Lee, Hyeon Gon
    Jung, Kijung
    Lim, Kisuk
    Kang, Youngkil
    Panchal, Manoj
    Pichel, German Perez
    Her, Namil
    Choi, Chang Ho
    [J]. FUSION ENGINEERING AND DESIGN, 2018, 134 : 132 - 136
  • [7] Design progress of the ITER vacuum vessel and ports
    Utin, Y
    Chuyanov, V
    Elio, F
    Ioki, K
    Jones, L
    Kornarov, V
    Kuzmin, E
    Morimoto, M
    Nakahira, M
    Sannazzaro, G
    [J]. FUSION ENGINEERING AND DESIGN, 2005, 75-79 : 571 - 575
  • [8] Manufacturing design of typical attachments in the vacuum vessel of ITER
    Kim, Yugyeong
    Privalov, Mikhail
    Jing, Juntao
    Mestric, Arnaud
    [J]. FUSION ENGINEERING AND DESIGN, 2021, 163
  • [9] Progress of ITER vacuum vessel
    Ioki, K.
    Bayon, A.
    Choi, C. H.
    Daly, E.
    Dani, S.
    Davis, J.
    Giraud, B.
    Gribov, Y.
    Hamlyn-Harris, C.
    Jun, C.
    Levesy, B.
    Kim, B. C.
    Kuzmin, E.
    Le Barbier, R.
    Martinez, J. -M.
    Pathak, H.
    Preble, J.
    Sa, J. W.
    Terasawa, A.
    Utin, Yu.
    Wang, X.
    [J]. FUSION ENGINEERING AND DESIGN, 2013, 88 (6-8) : 590 - 596
  • [10] 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