Heat transfer in pipes and rod bundles during flow of supercritical-pressure water

被引：4

作者：

Grabezhnaya, VA ^{[1
]}

Kirillov, PL ^{[1
]}

机构：

[1] State Sci Ctr Russian Federat, AI Leipunskii Phys & Power Engn Inst, Moscow, Russia

来源：

ATOMIC ENERGY | 2004年 / 96卷 / 05期

关键词：

Experimental Data; Heat Transfer; Current Idea; Hydraulic Resistance; Normal Heat;

D O I：

10.1023/B:ATEN.0000038103.86819.f8

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：

The current ideas on heat-transfer processes at supercritical pressure and on the hydraulic resistance in pipes and rod bundles are briefly presented in order to determine the computational relations for reactors cooled by water with supercritical parameters. The most widely used relations for calculating heat transfer in normal heat transfer regimes are analyzed and a comparison is made with the latest experimental data. Recommendations are made for calculating the hydraulic resistance coefficients and heat-transfer coefficients in pipes and rod bundles in a normal heat-transfer regime without degradation, which can be used to make new experimental and computational recommendations.

引用

页码：358 / 364

页数：7

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