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
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
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.