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
  • [31] Diagnostic integration solutions in the ITER first wall
    Martinez, Gonzalo
    Martin, Alex
    Watts, Christopher
    Veshchev, Evgeny
    Reichle, Roger
    Shigin, Pavel
    Sabourin, Flavien
    Gicquel, Stefan
    Mitteau, Raphael
    Gonzalez, Jorge
    FUSION ENGINEERING AND DESIGN, 2015, 98-99 : 1548 - 1551
  • [32] Analysis of a tile repair technique based on brazing process for ITER First Wall
    Perez-Pichel, German
    Porton, Mike
    Kirk, Simon
    Vizvary, Zsolt
    Eaton, Glenn
    FUSION ENGINEERING AND DESIGN, 2017, 122 : 186 - 195
  • [33] MULTIPHYSICS ENGINEERING ANALYSIS FOR ITER DIAGNOSTIC FIRST WALL AND SHIELD MODULE DESIGN
    Zhai, Y.
    Loesser, G.
    Smith, M.
    Wang, W.
    Udintsev, V.
    Giacomin, T.
    Khodak, A.
    Johnson, D.
    Feder, R.
    FUSION SCIENCE AND TECHNOLOGY, 2015, 68 (03) : 526 - 530
  • [34] Three dimensional neutronics analysis of the ITER first wall/shield module 13
    Smith, B.
    Wilson, P. P. H.
    Sawan, M. E.
    22ND IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, 2007, : 202 - 205
  • [35] Preliminary Analysis of In-Vessel First Wall Cooling Pipe Ruptures for ITER
    Lili Tong
    Yabing Li
    Jianming Yu
    Xuewu Cao
    Journal of Fusion Energy, 2015, 34 : 29 - 35
  • [36] Preliminary Analysis of In-Vessel First Wall Cooling Pipe Ruptures for ITER
    Tong, Lili
    Li, Yabing
    Yu, Jianming
    Cao, Xuewu
    JOURNAL OF FUSION ENERGY, 2015, 34 (01) : 29 - 35
  • [37] The JET ITER-like wall experiment: First results and lessons for ITER
    Horton, Lorne
    FUSION ENGINEERING AND DESIGN, 2013, 88 (6-8) : 434 - 439
  • [38] CFD Modelling of Saturated Flow Boiling in Heated Channels
    Hari, Jishnu
    Shajimon, Ebin Puthukattu
    Gopalakrishnan, Harikrishnan
    INTERNATIONAL CONFERENCE ON APPLIED MECHANICS AND OPTIMISATION (ICAMEO-2019), 2019, 2134
  • [39] CFD for subcooled flow boiling: Simulation of DEBORA experiments
    Krepper, Eckhard
    Rzehak, Roland
    NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (09) : 3851 - 3866
  • [40] CFD investigation and assessment of wall heat flux partitioning model for the prediction of high pressure subcooled flow boiling
    Murallidharan, Janani Srree
    Prasad, B. V. S. S. S.
    Patnaik, B. S. V.
    Hewitt, G. F.
    Badalassi, V.
    INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2016, 103 : 211 - 230