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THERMAL-HYDRAULIC ASSESSMENT OF HIGH HEAT-FLUX REMOVAL TECHNIQUES FOR FUSION APPLICATIONS
被引：5
|作者：
BOYD, RD
WONG, CPC
CHA, YS
机构：
[1] GA TECHNOL INC,SAN DIEGO,CA 92138
[2] ARGONNE NATL LAB,ARGONNE,IL 60439
关键词：
This paper is an assessment of three possible thermal-hydraulic;
high heat flux removal techniques which will result in adequate heat removal with minimum penalty from components in fusion reactors. The heat removal alternatives discussed are: (1) subcooled flow boiling (SFB) with water;
(2) high velocity helium gas convection;
and (3) liquid metal heat transfer in the presence of a magnetic field. The assessment emphasizes advantages;
disadvantages;
available data base;
and applicability of fusion component requirements. The reader is referred to ref. [1;
which is an expanded version of this assessment;
for additional details. Because of the relatively high heat flux levels and long pulse duration in the next generation of fusion reactors;
in-vessel components must be actively cooled. All fusion components will be heated nonuniformly over their surface and the surface area of most components vary from 0.1 m 2 to 103 m 2. Most components will be subjected to steady-state heat fluxes ranging * A portion of this work was performed at Sandia National Laboratories supported by the US Department of Energy under contract DE-AC04-76DP00789;
D O I：
10.1016/0029-5493(85)90049-4
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：
9
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页码：103 / 110
页数：8
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