Published 1994 | Version v1
Report

Large-scale boiling experiments of the flooded cavity concept for in-vessel core retention

Description

This paper presents results of ex-vessel boiling experiments performed in the CYBL (cylindrical boiling) facility, a reactor-scale facility which has a tank-within-a-tank design simulating the reactor vessel and the reactor cavity. Experiments with uniform and edge-peaked heat flux distributions up to 20 W/cm2 across the vessel bottom are performed. Boiling outside the reactor vessel is found to be subcooled nucleate boiling. The subcooling is mainly due to the gravity head which results from flooding the sides of the reactor vessel. The boiling process exhibits a cyclic pattern with four distinct phases: direct liquid/solid contact, bubble nucleation and growth, coalescence, and vapor mass dispersion (ejection). The results suggest that the flooded cavity in a passive PWR like the AP-600 should be capable of cooling the RPV in the central region of the lower head. 9 figs., 1 tab., 14 refs

Part of:
Large molten pool heat transfer

Additional details

Publishing Information

Imprint Title
Large molten pool heat transfer
Imprint Pagination
563 p.
Journal Page Range
p. 385-408.
Report number
NEA-CSNI-R--94-11

Conference

Title
Workshop on Large Molten Pool Heat Transfer.
Dates
9-11 Mar 1994.
Place
Grenoble (France).

INIS

Country of Publication
Nuclear Energy Agency of the OECD (NEA)
Country of Input or Organization
Nuclear Energy Agency of the OECD (NEA)
INIS RN
26037869
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CORE FLOODING SYSTEMS; CORIUM; HEAT FLUX; MELTDOWN; NUCLEATE BOILING; REACTOR SAFETY EXPERIMENTS; REACTOR VESSELS; SUBCOOLED BOILING; TEMPERATURE DISTRIBUTION
Descriptors DEC
ACCIDENTS; BOILING; CONTAINERS; ECCS; ENGINEERED SAFETY SYSTEMS; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS

Optional Information