Simulation of the Incident Helium Ingress into the Cryostat of the DEMO Fusion Reactor

被引:0
|
作者
Tekavcic, Matej [1 ]
Koncar, Bostjan [1 ]
Draksler, Martin [1 ]
Bachmann, Christian [2 ]
机构
[1] Jozef Stefan Inst, Jamova Cesta 39, SI-1000 Ljubljana, Slovenia
[2] Eurofus Consortium, PPPT Power Plant Phys & Technol, Boltzmannstr 2, D-85748 Garching, Germany
关键词
D O I
暂无
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
During a helium leak accident the cryostat is filled with helium gas, which causes the cryostat to cool down due to the heat transferred through the helium between the cryostat and the cryogenic magnet system. The scenario considered in this study assumes that the cryostat thermal shield (CTS) remains actively cooled at 80 K. Hence, only the heat transferred by natural convection of helium between the warm cryostat walls and the cold CTS is considered in the analysis. The helium natural convection in the isolated compartment between the CTS and the cryostat has been simulated to determine the heat transfer and temperature distributions on the cryostat walls, on the outside surrounded by the air at room temperature. The ANSYS-CFX code was used to run the steady-state simulations. The 2015 DEMO geometry with 18 equatorial port is used for the purpose of this study.
引用
收藏
页数:10
相关论文
共 50 条
  • [21] Simplification of blanket system for SlimCS fusion DEMO reactor
    Someya, Youji
    Takase, Haruhiko
    Utoh, Hiroyasu
    Tobita, Kenji
    Liu, Changle
    Asakura, Nobuyuki
    [J]. FUSION ENGINEERING AND DESIGN, 2011, 86 (9-11) : 2269 - 2272
  • [22] Numerical simulation of two-phase flow behavior in a fusion reactor during an ingress-of-coolant event
    Takase, K
    [J]. FUSION TECHNOLOGY, 1998, 34 (03): : 651 - 655
  • [23] A preliminary conceptual design study for Korean fusion DEMO reactor
    Kim, Keeman
    Kim, Hyoung Chan
    Oh, Sangjun
    Lee, Young Seok
    Yeom, Jun Ho
    Im, Kihak
    Lee, Gyung-Su
    Neilson, George
    Kessel, Charles
    Brown, Thomas
    Titus, Peter
    [J]. FUSION ENGINEERING AND DESIGN, 2013, 88 (6-8) : 488 - 491
  • [24] Torus configuration and materials selection on a fusion DEMO reactor, SlimCS
    Tobita, K.
    Nishio, S.
    Tanigawa, H.
    Enoeda, M.
    Isono, T.
    Nakamura, H.
    Tsuru, D.
    Suzuki, S.
    Hayashi, T.
    Tsuchiya, K.
    Hayashi, T.
    Nishitani, T.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2009, 386-88 : 888 - 892
  • [25] Design and analysis of robot for the maintenance of divertor in DEMO fusion reactor
    Li, Changyang
    Wu, Huapeng
    Eskelinen, Harri
    Siuko, Mikko
    Loving, Antony
    [J]. FUSION ENGINEERING AND DESIGN, 2019, 146 : 2092 - 2095
  • [26] Comparative evaluation of remote maintenance schemes for fusion DEMO reactor
    Utoh, Hiroyasu
    Tobita, Kenji
    Someya, Youji
    Asakura, Nobuyuki
    Sakamoto, Yoshiteru
    Hoshino, Kazuo
    Nakamura, Makoto
    [J]. FUSION ENGINEERING AND DESIGN, 2015, 98-99 : 1648 - 1651
  • [27] Activation analysis for sequential reactions of a fusion demo-reactor
    Yamauchi, M.
    Nishitani, T.
    Nishio, S.
    Hori, J.
    Kawasaki, H.
    [J]. FUSION SCIENCE AND TECHNOLOGY, 2007, 52 (04) : 781 - 785
  • [28] Engineering the Main Structures of the DEMO Fusion Reactor Magnet System
    Giannini, L.
    Boso, D.
    Corato, V.
    Muzzi, L.
    della Corte, A.
    [J]. IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2022, 32 (06)
  • [29] Study of impacts on tritium breeding ratio of a fusion DEMO reactor
    Zheng, Shanliang
    Todd, Thomas N.
    [J]. FUSION ENGINEERING AND DESIGN, 2015, 98-99 : 1915 - 1918
  • [30] Conceptual design of Japan's fusion DEMO reactor (JA DEMO) and superconducting coil issues
    Tobita, K.
    Utoh, H.
    Hiwatari, R.
    Miyoshi, Y.
    Tokunaga, S.
    Sakamoto, Y.
    Someya, Y.
    Asakura, N.
    Homma, Y.
    Nakajima, N.
    [J]. 31ST INTERNATIONAL SYMPOSIUM ON SUPERCONDUCTIVITY (ISS2018), 2019, 1293