On Calculating Heat Transfer and Pressure Drop of Supercritical-Pressure Coolants

Author:

Kurganov Vladimir A.1,Zeigarnik Yuri A.1,Maslakova Irina V.1

Affiliation:

1. Heat Transfer Division, Joint Institute for High Temperatures, Russian Academy of Sciences, ul. Izhorskaya 13, bld. 2, Moscow 125412, Russia e-mail:

Abstract

Specific features of thermophysical properties of single-phase supercritical-pressure (SCP) coolants and typical ranges of their thermodynamic state that determine heat-transfer regularities are presented. A brief analysis of the existing concepts on SCP-coolants heat transfer under turbulent flow in tube is given. Typical features of normal and deteriorated heat-transfer regimes are described. The simple classification of deteriorated heat-transfer regimes at high heat loads that make it possible to distinguish the causes and appraise a degree of heat-transfer deterioration danger is proposed. The results from the studies of the hydraulic-resistance structure under the regimes of normal and deteriorated heat transfer are considered and the conditions, when a one-dimensional (1-D) (homogeneous) flow model can be used in hydraulic calculations, are revealed. Using sounding measurements data, the interrelation between heat-transfer deterioration and radical changes in the averaged turbulent flow structure due to fluid thermal acceleration and Archimedes forces effects is analyzed. The recommendations on calculating normal heat transfer with an account of refined standards on thermophysical properties of water and carbon dioxide are presented. The review and analysis of the existing criteria for forecasting heat-transfer deterioration and assessing the boundaries of the normal heat-transfer range are given, and the correlations for describing deteriorated heat transfer are presented.

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Reference56 articles.

1. Nuclear Power as a Basic for FUTURE Electricity Generation;J. Nucl. Eng. Radiat. Sci.,2015

2. Changing Over to Supercritical Parameters—The Way to Advance Nuclear Power Stations With Water Cooled Reactors;Therm. Eng.,2001

3. Oka, Y., 2003, “Research and Development of the Supercritical: Pressure Light Water Cooled Reactors,” Proceedings of the 10th International Topical Meeting on Nuclear Thermal Hydraulics (NURETH-10), Seoul, Korea, Oct. 5–9.

4. The Use of Supercritical Parameters of a Coolant—A Promising Path to Development of Nuclear Plant Water-Cooled Reactors in the 21st Century;Therm. Eng.,2006

同舟云学术

1.学者识别学者识别

2.学术分析学术分析

3.人才评估人才评估

"同舟云学术"是以全球学者为主线,采集、加工和组织学术论文而形成的新型学术文献查询和分析系统,可以对全球学者进行文献检索和人才价值评估。用户可以通过关注某些学科领域的顶尖人物而持续追踪该领域的学科进展和研究前沿。经过近期的数据扩容,当前同舟云学术共收录了国内外主流学术期刊6万余种,收集的期刊论文及会议论文总量共计约1.5亿篇,并以每天添加12000余篇中外论文的速度递增。我们也可以为用户提供个性化、定制化的学者数据。欢迎来电咨询!咨询电话:010-8811{复制后删除}0370

www.globalauthorid.com

TOP

Copyright © 2019-2024 北京同舟云网络信息技术有限公司
京公网安备11010802033243号  京ICP备18003416号-3