Melt coolability modeling and comparison to MACE test results
- Resource Type
- Conference
- Authors
- Source
- Conference: 2. Organization for Economic Cooperation and Development (OECD)/Committee on the Safety of Nuclear Installations (CSNI) specialists meeting,Karlsruhe (Germany),1-3 Apr 1992; Other Information: PBD: [1992]
- Subject
- 22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE BWR TYPE REACTORS
REACTOR ACCIDENTS
PWR TYPE REACTORS
CORIUM
QUENCHING
CONCRETES
INTERACTIONS
HEAT TRANSFER
HYDRAULICS
REACTOR SAFETY
HEAT FLUX
MATHEMATICAL MODELS 220900
POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, BOILING WATER COOLED
POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED
MATHEMATICS AND COMPUTERS
- Language
- English
An important question in the assessment of severe accidents in light water nuclear reactors is the ability of water to quench a molten corium-concrete interaction and thereby terminate the accident progression. As part of the Melt Attack and Coolability Experiment (MACE) Program, phenomenological models of the corium quenching process are under development. The modeling approach considers both bulk cooldown and crust-limited heat transfer regimes, as well as criteria for the pool thermal hydraulic conditions which separate the two regimes. The model is then compared with results of the MACE experiments.