Magnetohydrodynamic pressure drops in geometric elements forming a HCLL blanket mock-up

被引:11
|
作者
Mistrangelo, C. [1 ]
Buehler, L. [1 ]
机构
[1] Karlsruhe Inst Technol, D-76021 Karlsruhe, Germany
基金
欧盟地平线“2020”;
关键词
Magnetohydrodynamic (MHD) experiments; Helium cooled blanket; Liquid metal; Pressure drop; Inertia effects;
D O I
10.1016/j.fusengdes.2011.03.011
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 helium cooled lead lithium (HCLL) blanket concept is one of the designs that will be tested and validated in the experimental reactor ITER. The liquid metal, which is slowly circulated in the blanket, interacts with the magnetic field that confines the fusion plasma leading to modifications of velocity and pressure distributions compared to the ones in hydrodynamic flows. Experiments have been performed to investigate magnetohydrodynamic flows in a scaled mock-up of a HCLL blanket. One of the aims is identifying the geometric elements that give rise to the main contributions to the total pressure head in the module. Parametric studies have been carried out to assess the influence of flow rate and magnetic field intensity on pressure drops. (C) 2011 Karlsruhe Institute of Technology (KIT). Published by Elsevier B.V. All rights reserved.
引用
收藏
页码:2304 / 2307
页数:4
相关论文
共 50 条
  • [31] Fabrication and thermal cycle testing of a first wall mock-up for ITER baffle blanket module
    Japan Atomic Energy Research Inst, Ibaraki-ken, Japan
    Fusion Technol, 3 pt 2 (908-913):
  • [32] Evaluation of tritium production rate in a blanket mock-up using a compact fusion neutron source
    Mukai, Keisuke
    Ogino, Yasuyuki
    Kobayashi, Makoto I.
    Mahmoud, Bakr
    Yagi, Juro
    Ogawa, Kunihiro
    Isobe, Mitsutaka
    Konishi, Satoshi
    NUCLEAR FUSION, 2021, 61 (04)
  • [33] Pre -analysis of the WCLL breeding blanket mock-up neutronics experiment at the frascati neutron generator
    Flammini, D.
    Angelone, M.
    Caiffi, B.
    Colangeli, A.
    Fonnesu, N.
    Mariano, G.
    Moro, F.
    Villari, R.
    FUSION ENGINEERING AND DESIGN, 2020, 156
  • [34] Optimization of the pressure drops in the helium in-module manifolds of the EU DEMO "Optimized Conservative" HCLL Breeding Blanket
    Domalapally, Phani Kumar
    Aubert, Julien
    Reungoat, Mathieu
    Vala, Ladislav
    FUSION ENGINEERING AND DESIGN, 2018, 136 : 852 - 858
  • [35] Numerical benchmarks TRIPOLI - MCNP with use of MCAM on FNG ITER bulk shield and FNG HCLL TBM mock-up experiments
    Fausser, Clement
    Lee, Yi-Kang
    Villari, Rosaria
    Zeng, Qin
    Zhang, Junjun
    Serikov, Arkady
    Trama, Jean-Christophe
    Gabriel, Franck
    FUSION ENGINEERING AND DESIGN, 2011, 86 (9-11) : 2135 - 2138
  • [36] Development and validation of the blanket First Wall mock-up model in RELAP5-3D
    Di Marcello, Valentino
    Ghidersa, Bradut-Eugen
    Jin, Xue Zhou
    Abou-Sena, Ali
    Stieglitz, Robert
    FUSION ENGINEERING AND DESIGN, 2018, 136 : 1534 - 1539
  • [37] Development of ceramic breeding zone models and mock-up of a demo blanket for in-pile irradiation testing
    Kapychev, V
    Davydov, D
    Demidov, V
    Kazennov, Y
    Tebus, V
    Frolov, V
    Shikov, A
    Shishkov, N
    Kovalenko, V
    Lopatkin, A
    Marachev, A
    Shishkin, V
    Strebkov, Y
    PLASMA DEVICES AND OPERATIONS, 2000, 8 (03): : 187 - 199
  • [38] Measurements of Thermal and Epithermal Neutron Spatial Distribution Using Activation Foils Inside a Fusion Blanket Mock-Up
    Ogino, Y.
    Kenjo, S.
    Sakabe, T.
    Mukai, K.
    Bakr, M.
    Yagi, J.
    Konishi, S.
    IEEE TRANSACTIONS ON PLASMA SCIENCE, 2023, 51 (08) : 2436 - 2442
  • [39] Simulations for practical measurement methods of spatial neutron distribution inside blanket mock-up irradiated with DT neutrons
    Ogino, Yasuyuki
    Mukai, Keisuke
    Yagi, Juro
    Konishi, Satoshi
    FUSION ENGINEERING AND DESIGN, 2021, 168
  • [40] Direct tritium measurement in lithium titanate for breeding blanket mock-up experiments with D-T neutrons
    Klix, A
    Ochiai, K
    Nishitani, T
    Takahashi, A
    FUSION ENGINEERING AND DESIGN, 2004, 70 (04) : 279 - 287