CFD analysis of flow boiling in the ITER first wall

被引:21
|
作者
Domalapally, Phani [1 ]
Rizzo, Enrico [2 ]
Richard, Laura Savoldi [1 ]
Subba, Fabio [1 ]
Zanino, Roberto [1 ]
机构
[1] Politecn Torino, Dipartimento Energet, I-10129 Turin, Italy
[2] Karlsruhe Inst Technol, Inst Tech Phys, Karlsruhe, Germany
关键词
Boiling; First wall; Two phase flow; Computational Fluid Dynamics;
D O I
10.1016/j.fusengdes.2012.01.024
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
This paper compares two Computational Fluid Dynamic (CFD) approaches for the analysis of flow boiling inside the first wall (FW) of the International Thermonuclear Experimental Reactor (ITER): (1) the Rohsenow model for nucleate boiling, seamlessly switching to the Volume of Fluid (VOF) approach for film boiling, as available in the commercial CFD code STAR-CCM+, (2) the Bergles-Rohsenow (BR) model, for which we developed a User Defined Function (UDF), implemented in the commercial code FLUENT. The physics of both models is described, and the results with different inlet conditions and heating levels are compared with experimental results obtained at the Efremov Institute, Russia. The performance of both models is compared in terms of accuracy and computational cost. (C) 2012 Elsevier B.V. All rights reserved.
引用
收藏
页码:556 / 560
页数:5
相关论文
共 50 条
  • [21] Thermal Modelling of ITER First Wall
    Brank, Matic
    Kos, Leon
    Pitts, Richard A.
    Simic, Gregor
    28TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE (NENE 2019), 2019,
  • [22] The design of the ITER first wall panels
    Mitteau, R.
    Calcagno, B.
    Chappuis, P.
    Eaton, R.
    Gicquel, S.
    Chen, J.
    Labusov, A.
    Martin, A.
    Merola, M.
    Raffray, R.
    Ulrickson, M.
    Zacchia, F.
    FUSION ENGINEERING AND DESIGN, 2013, 88 (6-8) : 568 - 570
  • [23] Sensitivity analysis for subcooled flow boiling using Eulerian CFD approach
    Vlcek, Daniel
    Sato, Yohei
    NUCLEAR ENGINEERING AND DESIGN, 2023, 405
  • [24] SOURCE PROFILE ANALYSIS FOR THE ITER FIRST WALL/SHIELD MODULE 13
    Smith, B.
    Wilson, P.
    Sawan, M.
    Bohm, T.
    FUSION SCIENCE AND TECHNOLOGY, 2009, 56 (01) : 57 - 61
  • [25] CFD for Subcooled Flow Boiling: Parametric Variations
    Rzehak, Roland
    Krepper, Eckhard
    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2013, 2013
  • [26] Application of analytical wall functions to CFD analysis of condensation flow
    Soma, Shu
    Ishigaki, Masahiro
    Abe, Satoshi
    Sibamoto, Yasuteru
    NUCLEAR ENGINEERING AND DESIGN, 2024, 416
  • [27] CFD Analysis of Subcooled Flow Boiling in 4 x 4 Rod Bundle
    Seo, Ye-Bon
    Paramanantham, SalaiSargunan S.
    Bak, Jin-Yeong
    Yun, Byongjo
    Park, Warn-Gyu
    APPLIED SCIENCES-BASEL, 2020, 10 (13):
  • [28] The interaction of the ITER first wall with magnetic perturbations
    Boozer, Allen H.
    NUCLEAR FUSION, 2021, 61 (04)
  • [29] Requirements for plasma and first wall measurements on ITER
    Costley, A. E.
    Andrew, P.
    Boivin, R. L.
    Ingesson, C.
    Johnson, D.
    Vayakis, G.
    Young, K.
    BURNING PLASMA DIAGNOSTICS, 2008, 988 : 27 - +
  • [30] Considerations in testing of ITER first wall mockups
    Tanaka, T. J.
    Nygren, R. E.
    Youchison, D. L.
    Ulfickson, M. A.
    FUSION ENGINEERING AND DESIGN, 2007, 82 (15-24) : 1884 - 1892