Two-fluid analysis of the thermal-hydraulic stability of ITER CS and TF super-conductors

被引:0
|
作者
Zanino, R [1 ]
Marinucci, C [1 ]
Savoldi, L [1 ]
机构
[1] Politecn Torino, Dipartimento Energet, I-10129 Turin, Italy
关键词
D O I
暂无
中图分类号
O414.1 [热力学];
学科分类号
摘要
Thermal-hydraulic stability of the two-channel cable-in-conduit conductors (CICC) foreseen for the central solenoid (CS) and the toroidal field (TF) Nb3Sn super-conducting coils of the International Thermonuclear Experimental Reactor (ITER) is analyzed with the two-fluid code MITHRANDIR [1]. In all external-heating scenarios considered, the computed stability margin is of the order of some 100 mJ/ccst. Extra-strands Cu addition typically leads to higher computed margins. MITHRANDIR estimates are typically conservative with respect to one-fluid results.
引用
收藏
页码:361 / 364
页数:4
相关论文
共 50 条
  • [21] Analysis of the Thermal-Hydraulic Effects of a Plasma Disruption on the DTT TF Magnets
    Bonifetto, R.
    De Bastiani, M.
    Di Zenobio, A.
    Muzzi, L.
    Turtu, S.
    Zanino, R.
    Zappatore, A.
    IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2022, 32 (06)
  • [22] Thermal-hydraulic analysis of a superheat BWR design using two fluid model
    Bahonar, M.
    Jahanfarnia, G.
    Gharib, M.
    PROGRESS IN NUCLEAR ENERGY, 2018, 107 : 172 - 183
  • [23] Thermal-hydraulic analysis of the ITER CCWS-1 cooling loop
    Agnello, Giuseppe
    Ciampichetti, Andrea
    Dell'Orco, Giovanni
    Di Maio, Pietro Alessandro
    Di Palma, Giuseppe
    Farinella, Francesco Maria
    Maggio, Sofia
    Vallone, Eugenio
    FUSION ENGINEERING AND DESIGN, 2025, 211
  • [24] Thermal-hydraulic analysis of the DEMO CS coil designed by CEA
    Dembkowska, Aleksandra
    Lewandowska, Monika
    Zani, Louis
    Lacroix, Benoit
    FUSION ENGINEERING AND DESIGN, 2021, 171
  • [25] Adjoint sensitivity analysis of the RELAP5/MOD3.2 two-fluid thermal-hydraulic code system - II: Applications
    Ionescu-Bujor, M
    Cacuci, DG
    NUCLEAR SCIENCE AND ENGINEERING, 2000, 136 (01) : 85 - 121
  • [26] Adjoint sensitivity analysis of the RELAP5/MOD3.2 two-fluid thermal-hydraulic code system - I: Theory
    Cacuci, DG
    Ionescu-Bujor, M
    NUCLEAR SCIENCE AND ENGINEERING, 2000, 136 (01) : 59 - 84
  • [27] 3D thermal-hydraulic analysis of two irregular field joints for the ITER vacuum vessel
    Savoldi, Laura
    Bonifetto, Roberto
    Izquierdo, Jesus
    Le Barbier, Robin
    Utin, Yuri
    Zanino, Roberto
    FUSION ENGINEERING AND DESIGN, 2015, 98-99 : 1605 - 1609
  • [28] Thermal-hydraulic Stability Analysis of Nuclear Heating Reactors
    李金才
    高祖瑛
    张作义
    Tsinghua Science and Technology, 1996, (01) : 23 - 26
  • [29] THERMAL-HYDRAULIC STABILITY ANALYSIS OF INTERCONNECTED BOILING CHANNELS
    TALEYARKHAN, R
    PODOWSKI, M
    LAHEY, RT
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1981, 39 : 1052 - 1053
  • [30] High heat flux thermal-hydraulic analysis of ITER divertor and blanket systems
    Raffray, AR
    Chiocchio, S
    Ioki, K
    Krassovski, D
    Kubik, D
    Tivey, R
    FUSION ENGINEERING AND DESIGN, 1998, 39-40 : 323 - 331