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Titolo:
Measurement of critical heat flux for narrow annuli submerged in saturatedwater
Autore:
Kim, SH; Baek, WP; Chang, SH;
Indirizzi:
Korea Adv Inst Sci & Technol, Dept Nucl Engn, Taejon 305701, South Korea Korea Adv Inst Sci & Technol Taejon South Korea 305701 5701, South Korea
Titolo Testata:
NUCLEAR ENGINEERING AND DESIGN
fascicolo: 1-2, volume: 199, anno: 2000,
pagine: 41 - 48
SICI:
0029-5493(200006)199:1-2<41:MOCHFF>2.0.ZU;2-J
Fonte:
ISI
Lingua:
ENG
Soggetto:
SEVERE ACCIDENT; REACTOR VESSEL;
Tipo documento:
Article
Natura:
Periodico
Settore Disciplinare:
Engineering, Computing & Technology
Citazioni:
13
Recensione:
Indirizzi per estratti:
Indirizzo: Chang, SH Korea Adv Inst Sci & Technol, Dept Nucl Engn, 373-1 Kusong Dong,Taejon 305701, South Korea Korea Adv Inst Sci & Technol 373-1 Kusong Dong Taejon South Korea 305701
Citazione:
S.H. Kim et al., "Measurement of critical heat flux for narrow annuli submerged in saturatedwater", NUCL ENG DE, 199(1-2), 2000, pp. 41-48

Abstract

An experimental study has been performed to improve understanding of boiling phenomena and critical heat flux (CHF) in narrow gaps. The experiment has been performed with annular test sections submerged in a pool of saturated water under atmospheric pressure with the following conditions: outer diameter of inner tube of 19 mm; heated length of 200 mm; annular gap sizes of0.5-3.5 mm, and inclination angles from horizontal to vertical positions. The experimental results reveal that the CHF increases with the gap size and the inclination angle. A one-dimensional two-phase model with a modified friction factor correlation is suggested to predict the CHF condition. The developed model is also compared with other CHF data. (C) 2000 Elsevier Science S.A. All rights reserved.

ASDD Area Sistemi Dipartimentali e Documentali, Università di Bologna, Catalogo delle riviste ed altri periodici
Documento generato il 11/07/20 alle ore 20:53:58