Critical heat flux of subcooled flow boiling in swirl tubes relevant to high-heat-flux components
Abstract
It is necessary to accurately determine the critical heat flux (CHF) of cooling systems used in fusion reactors. Currently, sufficiently accurate CHF correlations for one-sided heating have not been established. A design method for subcooled boiling cooling systems using swirl tubes is described. From a review of existing work under uniform heating conditions, the correlations of Gunther and Nariai-Inasaka are recommended for smooth and swirl flow, respectively. The effects of thermal conductivity and geometry of the cooling sections on both the nouniformity factor and the peaking factor were investigated by solving a heat conduction equation. For swirl flow under one-sided heating, the CHF multiplier increases with the increasing nonuniformity factor. Design criteria for subcooled boiling swirl-tube cooling systems are presented. 33 refs., 13 figs., 4 tabs.
- Authors:
-
- Ship Research Inst., Tokyo (Japan)
- Univ. of Tsukuba, Ibaraki (Japan)
- Publication Date:
- OSTI Identifier:
- 374456
- Resource Type:
- Journal Article
- Journal Name:
- Fusion Technology
- Additional Journal Information:
- Journal Volume: 29; Journal Issue: 4; Other Information: PBD: Jul 1996
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 22 NUCLEAR REACTOR TECHNOLOGY; 42 ENGINEERING NOT INCLUDED IN OTHER CATEGORIES; 70 PLASMA PHYSICS AND FUSION; 99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; REACTOR COOLING SYSTEMS; CRITICAL HEAT FLUX; DESIGN; FLUID FLOW; REACTOR COMPONENTS; THERMONUCLEAR REACTORS; SUBCOOLED BOILING; TUBES; MATHEMATICAL MODELS; THERMAL CONDUCTIVITY; THERMAL CONDUCTION; VORTEX FLOW
Citation Formats
Inasaka, Fujio, and Nariai, Hideki. Critical heat flux of subcooled flow boiling in swirl tubes relevant to high-heat-flux components. United States: N. p., 1996.
Web.
Inasaka, Fujio, & Nariai, Hideki. Critical heat flux of subcooled flow boiling in swirl tubes relevant to high-heat-flux components. United States.
Inasaka, Fujio, and Nariai, Hideki. 1996.
"Critical heat flux of subcooled flow boiling in swirl tubes relevant to high-heat-flux components". United States.
@article{osti_374456,
title = {Critical heat flux of subcooled flow boiling in swirl tubes relevant to high-heat-flux components},
author = {Inasaka, Fujio and Nariai, Hideki},
abstractNote = {It is necessary to accurately determine the critical heat flux (CHF) of cooling systems used in fusion reactors. Currently, sufficiently accurate CHF correlations for one-sided heating have not been established. A design method for subcooled boiling cooling systems using swirl tubes is described. From a review of existing work under uniform heating conditions, the correlations of Gunther and Nariai-Inasaka are recommended for smooth and swirl flow, respectively. The effects of thermal conductivity and geometry of the cooling sections on both the nouniformity factor and the peaking factor were investigated by solving a heat conduction equation. For swirl flow under one-sided heating, the CHF multiplier increases with the increasing nonuniformity factor. Design criteria for subcooled boiling swirl-tube cooling systems are presented. 33 refs., 13 figs., 4 tabs.},
doi = {},
url = {https://www.osti.gov/biblio/374456},
journal = {Fusion Technology},
number = 4,
volume = 29,
place = {United States},
year = {Mon Jul 01 00:00:00 EDT 1996},
month = {Mon Jul 01 00:00:00 EDT 1996}
}