Numerical simulations on gaseous flow and heat transfer in multiple narrow channels of IFMIF High Flux Test Module

被引:3
|
作者
Chen, Yuming [1 ]
Arbeiter, Frederik [1 ]
机构
[1] Karlsruhe Inst Technol, Inst Neutron Phys & Reactor Technol, D-76344 Eggenstein Leopoldshafen, Germany
关键词
IFMIF; CFD; Conjugate heat transfer; Numerical simulation; Transition flows; Narrow channels; GAS-FLOW; TURBULENCE MODELS; INTERMITTENT; BREAKDOWN;
D O I
10.1016/j.fusengdes.2013.04.038
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 International Fusion Materials Irradiation Facility (IFMIF) is designated to generate a materials irradiation database for the future fusion reactors. In the High Flux Test Module (HFTM) the test specimens will undergo a severe structural damage caused by neutron fluxes. The HFTM will be with helium gas. This paper presents the comprehensive thermo-hydraulic simulations of the HFTM as a part of the design activities. The turbulence models were assessed by comparing the simulations with in-house annular channel experiments. Since the required coolant flow rates are different for different compartments, multiple fluid domains were employed and simulated with appropriate turbulence (laminar) models individually. The flow distributions and heat transfer characteristics among various HFTM sub-channels will be discussed. Sensitivity study was carried out to assess the impacts of several factors on the simulation results. (C) 2013 Karlsruhe Institute of Technology (KIT). Published by Elsevier B.V. All rights reserved.
引用
收藏
页码:2814 / 2824
页数:11
相关论文
共 50 条
  • [1] NUMERICAL SIMULATIONS AND EXPERIMENTS ON GASEOUS FLOW AND HEAT TRANSFER IN MULTIPLE NARROW CHANNELS IN TRANSITION REGION
    Chen, Yuming
    Klein, Christine
    Arbeiter, Frederik
    Ibaceta, German
    PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 3, 2014,
  • [2] Numerical simulation of turbulent flow and heat transfer in a cooling channel of ifmif high flux test module
    Ebara, Shinji
    Nakaharai, Hiroyuki
    Yokomine, Takehiko
    Shimizu, Akihiko
    FUSION SCIENCE AND TECHNOLOGY, 2007, 52 (04) : 786 - 790
  • [3] Flow and heat transfer characteristics of helium cooled IFMIF High Flux Test Module
    Chen, Yuming
    Arbeiter, Frederik
    FUSION ENGINEERING AND DESIGN, 2012, 87 (5-6) : 530 - 534
  • [4] Transient conjugated heat transfer within IFMIF high flux test module
    Chen, Y.
    Arbeiter, F.
    Heinzel, V.
    Schlindwein, G.
    NUCLEAR ENGINEERING AND DESIGN, 2012, 249 : 172 - 179
  • [5] Large-eddy simulation of turbulent flow and heat transfer in a mildly expanded channel of IFMIF high flux test module
    Ebara, Shinji
    Yokomine, Takehiko
    Shimizu, Akihiko
    FUSION ENGINEERING AND DESIGN, 2007, 82 (15-24) : 2504 - 2509
  • [6] Numerical study of conjugated heat transfer for DONES high flux test module
    Gordeev, Sergej
    Schwab, Florian
    Arbeiter, Frederik
    Qiu, Yuefeng
    FUSION ENGINEERING AND DESIGN, 2019, 146 : 609 - 613
  • [7] Numerical simulations on natural convective heat transfer and active cooling of IFMIF Test Cell
    Chen, Yuming
    Arbeiter, Frederik
    Heinzel, Volker
    Kondo, Keitaro
    Mittwollen, Martin
    Tian, Kuo
    FUSION ENGINEERING AND DESIGN, 2014, 89 (9-10) : 2230 - 2234
  • [8] Development and validation status of the IFMIF High Flux Test Module
    Arbeiter, Frederik
    Abou-Sena, Ali
    Chen, Yuming
    Dolensky, Bernhard
    Heupel, Tobias
    Klein, Christine
    Scheel, Nicola
    Schlindwein, Georg
    FUSION ENGINEERING AND DESIGN, 2011, 86 (6-8) : 607 - 610
  • [9] Numerical examination of temperature control in helium-cooled high flux test module of IFMIF
    Ebara, Shinji
    Yokomine, Takehiko
    Shimizu, Akihiko
    FUSION ENGINEERING AND DESIGN, 2007, 82 (01) : 61 - 72
  • [10] Study on flow and heat transfer characteristics of liquid metal flow in narrow rectangular channels under high heat flux
    Zhang, Xue
    Feng, Wenpei
    Yu, Hongxing
    Deng, Jian
    Du, Sijia
    Wang, Xiaoyu
    FRONTIERS IN ENERGY RESEARCH, 2024, 12