EX-VESSEL BOILING EXPERIMENTS - LABORATORY-SCALE AND REACTOR-SCALE TESTING OF THE FLOODED CAVITY CONCEPT FOR IN-VESSEL CORE RETENTION .2. REACTOR-SCALE BOILING EXPERIMENTS OF THE FLOODED CAVITY CONCEPT FOR IN-VESSEL CORE RETENTION
Ty. Chu et al., EX-VESSEL BOILING EXPERIMENTS - LABORATORY-SCALE AND REACTOR-SCALE TESTING OF THE FLOODED CAVITY CONCEPT FOR IN-VESSEL CORE RETENTION .2. REACTOR-SCALE BOILING EXPERIMENTS OF THE FLOODED CAVITY CONCEPT FOR IN-VESSEL CORE RETENTION, Nuclear Engineering and Design, 169(1-3), 1997, pp. 89-99
This paper summarizes the results of a reactor-scale ex-vessel boiling
experiment for assessing the flooded cavity design of the heavy water
new production reactor. The simulated reactor vessel has a cylindrica
l diameter of 3.7 m and a torispherical bottom head. Boiling outside t
he reactor vessel was found to be subcooled nucleate boiling. The subc
ooling mainly results from the gravity head, which in turn results fro
m flooding the side of the reactor vessel. The boiling process exhibit
s a cyclic pattern with four distinct phases: direct liquid-solid cont
act. bubble nucleation and growth, coalescence, and vapor mass dispers
ion. The results show that, under prototypic heat load and heat flux d
istributions, the flooded cavity will be effective for in-vessel core
retention in the heavy water new production reactor. The results also
demonstrate that the heat dissipation requirement for in-vessel core r
etention, for the central region of the lower head of an AP-600 advanc
ed light water reactor, can be met with the flooded cavity design. (C)
1997 Elsevier Science S.A.