Nonequilibrium flashing model for rapid pressure transients
Description
A detailed, microscopic model for the nonequilibrium flashing of water is coupled to equations describing the bulk liquid state in order to calculate rapid pressure response to an induced liquid strain. The flashing model is predicated on the dynamics of a single bubble growing in an infinite liquid, and it encompasses both the inertia and conduction-limited regimes of bubble growth. The analysis is valid at high temperatures. It is not limited by the assumption of a thin thermal boundary layer for the bubble or by a prescribed boundary layer shape. The analysis can predict arbitrary pressure transients, both decompressive and recompressive. The flashing model involves the solution of a system of ordinary and partial differential equations constituting a classic moving-boundary problem. The solution is obtained numerically by the method of lines and by the use of automatic software
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01 as DE82007639.Files
13695945.pdf
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Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 37 p.
- Report number
- CONF-810804--24
Conference
- Title
- 20. national heat transfer conference.
- Dates
- 2 - 5 Aug 1981.
- Place
- Milwaukee, WI, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 13695945
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FLASH HEATING; HEAT TRANSFER; HYDRAULICS; HYDRODYNAMICS; LOSS OF COOLANT; MATHEMATICAL MODELS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR SAFETY; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENERGY TRANSFER; FLUID FLOW; FLUID MECHANICS; HEATING; MECHANICS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS