Recent experimental and analytical results of BNL direct containment heating programs
Conference
·
OSTI ID:7011258
The direct containment heating (DCH) scenario involves high-pressure ejection of molten core material from the reactor vessel into the region beneath the vessel and into various subcompartments of the containment building. The stored energy in the melt consists of the sensible energy of melt and the chemical reaction energy of the various components assuming that they can react with either the oxygen or the steam within containment. The metallic phase may first react with steam, if local conditions permit, and thereby produce hydrogen. The hydrogen may then burn at some later time at a different location. In order to predict the containment response, one must follow the melt through the various subcompartments of the containment building, while computing the integrated release of energy from the melt to the containment atmosphere and the quantity of hydrogen produced during the time period that the melt is suspended. The BNL research program in the area of direct containment heating is directed towards the development of a methodology to predict the hydrodynamic, chemical and thermal interactions which could take place in three regions of PWR containment buildings: the reactor cavity, the intermediate compartments (e.g., steam generator room) and the containment dome. Separate effects, scaled experiments are performed related to selected aspects of the DCH problem, and analytical models are developed to characterize the relevant phenomena.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA); Nuclear Regulatory Commission, Washington, DC (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 7011258
- Report Number(s):
- BNL-NUREG-39056; CONF-8610135-42; ON: TI87004178
- Country of Publication:
- United States
- Language:
- English
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·
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·
OSTI ID:5955314
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACCIDENTS
BUILDINGS
CONTAINERS
CONTAINMENT
CORIUM
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HEATING
HYDRAULICS
MECHANICS
MELTDOWN
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR VESSELS
REACTORS
RESEARCH PROGRAMS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACCIDENTS
BUILDINGS
CONTAINERS
CONTAINMENT
CORIUM
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HEATING
HYDRAULICS
MECHANICS
MELTDOWN
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR VESSELS
REACTORS
RESEARCH PROGRAMS
WATER COOLED REACTORS
WATER MODERATED REACTORS