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
下载
收藏
页码:361 / 364
页数:4
相关论文
共 50 条
  • [41] 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.
    FUSION ENGINEERING AND DESIGN, 2015, 92 : 69 - 74
  • [42] Thermal-hydraulic modeling and analysis of the Water Cooling System for the ITER Test Blanket Module
    Ciurluini, Cristiano
    Giannetti, Fabio
    Tincani, Amelia
    Del Nevo, Alessandro
    Caruso, Gianfranco
    Ricapito, Italo
    Cismondi, Fabio
    FUSION ENGINEERING AND DESIGN, 2020, 158
  • [43] 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
    ADVANCES IN CRYOGENIC ENGINEERING, VOLS. 49A AND B, 2004, 710 : 685 - 692
  • [44] Thermal-hydraulic analysis of a candidate design for ITER divertor neutron flux monitor (DNFM)
    Tanchuk, Victor
    Alexandrov, Evgeny
    Batyunin, Alexander
    Kashchuk, Yuri
    Korban, Svetlana
    Lyublin, Boris
    Obudovsky, Sergey
    Senik, Konstantin
    FUSION ENGINEERING AND DESIGN, 2013, 88 (6-8) : 1244 - 1248
  • [45] A linear stability analysis of supercritical water reactors, (I) thermal-hydraulic stability
    Yi, TT
    Koshizuka, S
    Oka, Y
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2004, 41 (12) : 1166 - 1175
  • [46] Stability analysis of two-fluid dark energy models
    Mishra, B.
    Esmaeili, Fakhereh Md
    Ray, Pratik P.
    Tripathy, S. K.
    PHYSICA SCRIPTA, 2021, 96 (04)
  • [47] Results of thermal hydraulic measurements on two 15 kA ITER style cable in conduit conductors
    Rousset, B
    Duchateau, JL
    Gauthier, A
    Martinez, A
    Seyfert, P
    Weisend, J
    ADVANCES IN CRYOGENIC ENGINEERING, VOL 41, PTS A AND B, 1996, : 505 - 512
  • [48] Thermal-Hydraulic Test and Analysis of the ENEA TF Conductor Sample for the EU DEMO Fusion Reactor
    Bonifetto, Roberto
    Bruzzone, Pierluigi
    Corato, Valentina
    Muzzi, Luigi
    Savoldi, Laura
    Stepanov, Boris
    Zanino, Roberto
    Zappatore, Andrea
    IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2018, 28 (04)
  • [49] Conceptual design overview of the ITER WCLL Water Cooling System and supporting thermal-hydraulic analysis
    Ciurluini, C.
    Narcisi, V
    Tincani, A.
    Ferrer, C. Ortiz
    Giannetti, F.
    FUSION ENGINEERING AND DESIGN, 2021, 171
  • [50] Neutronic, thermal-hydraulic and stress analysis of RF lithium cooled test blanket module for ITER
    Vitkovsky, IV
    Golovanov, MM
    Divavin, VA
    Kirillov, IR
    Lipko, AV
    Malkov, AA
    Kartashev, IA
    Komarov, VM
    Ogorodnikov, AP
    Schipakin, OL
    FUSION ENGINEERING AND DESIGN, 2000, 49-50 : 703 - 707