EX-VESSEL BOILING EXPERIMENTS - LABORATORY-SCALE AND REACTOR-SCALE TESTING OF THE FLOODED CAVITY CONCEPT FOR IN-VESSEL CORE RETENTION .1. OBSERVATION OF QUENCHING OF DOWNWARD-FACING SURFACES

Citation
Ty. Chu et al., EX-VESSEL BOILING EXPERIMENTS - LABORATORY-SCALE AND REACTOR-SCALE TESTING OF THE FLOODED CAVITY CONCEPT FOR IN-VESSEL CORE RETENTION .1. OBSERVATION OF QUENCHING OF DOWNWARD-FACING SURFACES, Nuclear Engineering and Design, 169(1-3), 1997, pp. 77-88
Citations number
18
Categorie Soggetti
Nuclear Sciences & Tecnology
ISSN journal
00295493
Volume
169
Issue
1-3
Year of publication
1997
Pages
77 - 88
Database
ISI
SICI code
0029-5493(1997)169:1-3<77:EBE-LA>2.0.ZU;2-0
Abstract
This paper presents the results of a series of quenching experiments t o examine the boiling curve of relative large downward-facing surfaces . The test masses are 61 cm in diameter and the downward-facing surfac e is either flat or curved. The work is motivated by the need to asses s the ex-vessel boiling process for in-vessel core retention. The crit ical heat flux is found to be approximately 50 W cm(-2). The nucleate boiling regime and the critical heat flux regime are found to be chara cterized by cyclic two-phase flow patterns. (C) 1997 Elsevier Science S.A.