Fuel-coolant interaction in a shock tube with initially-established film boiling. [PWR; BWR]
Conference
·
OSTI ID:6922312
A new mode of thermal interaction has been employed, in which liquid metal is melted in a crucible within a shock tube; the coolant level is raised to overflow the crucible and establish subcooled film boiling with known bulk metal temperature; and a pressure shock is then initiated. With water and lead-tin alloy an initial splash of metal may be obtained after the vapor film has collapsed, due primarily to thermal interaction, followed by a successive cycle of bubble growth and collapse. To obtain large interactions, the interfacial contact temperature must exceed the spontaneous nucleation temperature of the coolant. Other cutoff behavior is observed with respect to the initial system pressure and temperatures and with the shock pressure and rise time. Experiments with butanol and lead-tin alloy show only relatively mild interactions. Qualitative explanations are proposed for the different behaviors of the two liquids.
- Research Organization:
- Northwestern Univ., Evanston, IL (USA). Dept. of Chemical Engineering
- DOE Contract Number:
- AC02-76ET37210
- OSTI ID:
- 6922312
- Report Number(s):
- CONF-790816-105; ON: DE84013202
- Country of Publication:
- United States
- Language:
- English
Similar Records
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Fuel-coolant interactions in a shock tube geometry
Journal Article
·
Tue May 01 00:00:00 EDT 1979
· Nucl. Sci. Eng.; (United States)
·
OSTI ID:6266403
Subcooled and low quality film boiling of water in vertical flow at atmospheric pressure. [PWR; BWR]
Technical Report
·
Sat Aug 01 00:00:00 EDT 1981
·
OSTI ID:5274332
Fuel-coolant interactions in a shock tube geometry
Journal Article
·
Fri Nov 30 23:00:00 EST 1979
· Nucl. Technol.; (United States)
·
OSTI ID:5712965
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
BOILING
BWR TYPE REACTORS
CORIUM
DATA
ENERGY TRANSFER
EXPERIMENTAL DATA
FILM BOILING
FLUID MECHANICS
FUEL-COOLANT INTERACTIONS
HEAT TRANSFER
HYDRAULICS
INFORMATION
MECHANICS
MELTDOWN
MOLTEN METAL-WATER REACTIONS
NUMERICAL DATA
PHASE TRANSFORMATIONS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
SHOCK TUBES
TEMPERATURE DEPENDENCE
TEMPERATURE GRADIENTS
TEST FACILITIES
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
BOILING
BWR TYPE REACTORS
CORIUM
DATA
ENERGY TRANSFER
EXPERIMENTAL DATA
FILM BOILING
FLUID MECHANICS
FUEL-COOLANT INTERACTIONS
HEAT TRANSFER
HYDRAULICS
INFORMATION
MECHANICS
MELTDOWN
MOLTEN METAL-WATER REACTIONS
NUMERICAL DATA
PHASE TRANSFORMATIONS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
SHOCK TUBES
TEMPERATURE DEPENDENCE
TEMPERATURE GRADIENTS
TEST FACILITIES
WATER COOLED REACTORS
WATER MODERATED REACTORS