Attack of fragmented-core debris on concrete in the presence of water. [PWR; BWR]
Conference
·
OSTI ID:6733184
In the unlikely event that core debris escapes the reactor pressure vessel, the interactions of the debris with concrete, structural materials, and coolant become the driving force for severe accident phenomena. The Ex-Vessel Core Debris Interactions Program at Sandia National Laboratories is an experimental research effort to characterize these interactions and the magnitude of safety-related phenomena such as flammable gas generation, aerosol production, fission product release, and concrete attack. Major areas of study within the program include molten core simultants in contact with concrete, high pressure melt streaming into scaled reactor cavities, the addition of coolant to high-temperature melt/concrete interactions, and the attack of hot, solid core debris on concrete. This paper describes results from the last of these efforts, i.e., hot, but not molten debris attacking concrete.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6733184
- Report Number(s):
- SAND-82-2184C; CONF-821037-20; ON: DE83001173
- Country of Publication:
- United States
- Language:
- English
Similar Records
Hydrogen production during fragmented debris/concrete interactions. [PWR; BWR]
Model for superheated debris-bed quench for severe-accident containment calculations. [PWR; BWR]. CONF-831047--85
Gas bubbling-enhanced film boiling of Freon-11 on liquid metal pools. [PWR; BWR]
Conference
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:6607126
Model for superheated debris-bed quench for severe-accident containment calculations. [PWR; BWR]. CONF-831047--85
Conference
·
Mon Aug 01 00:00:00 EDT 1983
·
OSTI ID:5845836
Gas bubbling-enhanced film boiling of Freon-11 on liquid metal pools. [PWR; BWR]
Conference
·
Mon Dec 31 23:00:00 EST 1984
·
OSTI ID:5869187
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT
BUILDING MATERIALS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CONCRETES
CONTAINMENT
CONTAINMENT BUILDINGS
CORIUM
ELEMENTS
HYDROGEN
MATERIALS
MELTDOWN
NONMETALS
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
TEMPERATURE GRADIENTS
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT
BUILDING MATERIALS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CONCRETES
CONTAINMENT
CONTAINMENT BUILDINGS
CORIUM
ELEMENTS
HYDROGEN
MATERIALS
MELTDOWN
NONMETALS
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
TEMPERATURE GRADIENTS
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS