Fuel-coolant interaction in a shock tube with initially-established film boiling
Description
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
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01; 1 as DE84013202.Files
16010896.pdf
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Additional details
Additional titles
- Augmented title (English)
- PWR; BWR
Publishing Information
- Imprint Pagination
- 17 p.
- Report number
- CONF-790816--105
Conference
- Title
- International meeting on fast reactor safety technology.
- Dates
- 19-23 Aug 1979.
- Place
- Seattle, WA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16010896
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BWR TYPE REACTORS; CORIUM; EXPERIMENTAL DATA; FILM BOILING; FUEL-COOLANT INTERACTIONS; HEAT TRANSFER; HYDRAULICS; MELTDOWN; MOLTEN METAL-WATER REACTIONS; PWR TYPE REACTORS; REACTOR SAFETY; SHOCK TUBES; SPATIAL DISTRIBUTION; TEMPERATURE DEPENDENCE; TEMPERATURE DISTRIBUTION; TESTING
- Descriptors DEC
- ACCIDENTS; BOILING; DATA; DISTRIBUTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; PHASE TRANSFORMATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS