NORMAL FLOW HEAT-EXCHANGER FOR DIVERTOR PANEL COOLING

被引：7

作者：

IZENSON, MG

VALENZUELA, JA

机构：

来源：

FUSION TECHNOLOGY | 1992年 / 21卷 / 03期

关键词：

D O I：

10.13182/FST92-A29984

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 cooling offers safety advantages for fusion reactors because helium is single-phase and chemically inert. The Normal Flow Heat Exchanger (NFHX) enables highly efficient heat transfer to helium with low pressure drops at high heat fluxes. Thus, the NFHX enables helium cooling of divertor panels in Tokamak reactors and potentially enhances the safety of fusion power production. This paper explains the NFHX concept, presents the current status of the technology, and shows how the NFHX can be used to cool divertor panels in Tokamak reactors.

引用

页码：1828 / 1834

页数：7