Efficient helium cooling methods for nuclear fusion devices: Status and prospects

被引:18
作者
Ihli, T. [1 ]
Ilic, M. [1 ]
机构
[1] Forschungszentrum Karlsruhe, Inst Reaktorsicherheit, D-76344 Eggenstein Leopoldshafen, Germany
关键词
Helium; Divertor; Blanket; Jet; Impingement; Surface roughness; DEMO; DIVERTOR CONCEPT; HEAT-TRANSFER; DESIGN; PERFORMANCE; PARALLEL; RIBS;
D O I
10.1016/j.fusengdes.2009.01.008
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
Helium-cooled reactors offer several important advantages as the helium is an inert and neutron transparent gas. compatible with high outlet temperatures and all structural and functional materials considered for plasma facing components. On the other hand, during the power plant studies performed up to now it became evident, that the helium pumping power could become very high if standard cooling methods based on hydraulically smooth cooling channels would be applied and that a very high heat fluxin the divertor can only be achieved when using sophisticated gas cooling methods. In relation to this the main focus in this paper is on advanced gas cooling technology applications developed at Forschungszentrum Karlsruhe (FZK)for the main in-vessel components blanket/first wall and divertor of future fusion power reactors. Among a large number of considered cooling technologies the V-rib-based surface roughness approach for the first wall and the multiple jet impingement cooling technique for the divertor were identified as suitable and advantageous methods. The paper presents the main parameters to be considered and an evaluation of the achievable cooling performance in both cases. (C) 2009 Elsevier B.V. All rights reserved.
引用
收藏
页码:964 / 968
页数:5
相关论文
共 6 条
[1]   HIGH-PERFORMANCE HEAT-TRANSFER DUCTS WITH PARALLEL BROKEN AND V-SHAPED BROKEN RIBS [J].
HAN, JC ;
ZHANG, YM .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 1992, 35 (02) :513-523
[2]   AUGMENTED HEAT-TRANSFER IN SQUARE CHANNELS WITH PARALLEL, CROSSED, AND V-SHAPED ANGLED RIBS [J].
HAN, JC ;
ZHANG, YM ;
LEE, CP .
JOURNAL OF HEAT TRANSFER-TRANSACTIONS OF THE ASME, 1991, 113 (03) :590-596
[3]   Design and performance study of the helium-cooled T-tube divertor concept [J].
Ihli, T. ;
Raffray, A. R. ;
Abdel-Khalik, S. I. ;
Shin, S. .
FUSION ENGINEERING AND DESIGN, 2007, 82 (03) :249-264
[4]   An advanced He-cooled divertor concept: Design, cooling technology, and thermohydraulic analyses with CFD [J].
Ihli, T ;
Kruessmann, R ;
Ovchinnikov, I ;
Norajitra, P ;
Kuznetsov, V ;
Giniyatulin, R .
FUSION ENGINEERING AND DESIGN, 2005, 75-79 (75-79) :371-375
[5]   Thermohydraulic experimental design for the European Helium-Cooled-Pebble-Bed Test Blanket Module [J].
Ilic, M. ;
Kiss, B. ;
Ihli, T. .
FUSION ENGINEERING AND DESIGN, 2008, 83 (7-9) :1253-1257
[6]   He-cooled divertor development for DEMO [J].
Norajitra, P. ;
Giniyatulin, R. ;
Ihli, T. ;
Janeschitz, G. ;
Krauss, W. ;
Kruessmann, R. ;
Kuznetsov, V. ;
Mazul, I. ;
Widak, V. ;
Ovchinnikov, I. ;
Ruprecht, R. ;
Zeep, B. .
FUSION ENGINEERING AND DESIGN, 2007, 82 (15-24) :2740-2744