Published August 1980
| Version v1
Report
Evaluation of two bubble-detachment models for two-phase flow
Description
Two-phase flows with attached wall bubbles are considered as flows in roughened ducts with roughness elements equal in magnitude to the bubble detachment diameters determined by a force balance analysis. Two methods for determining the drag component of the forces acting on a bubble give distinctly different mixing-length theory expressions for velocity profile, friction factor, and void fraction. Available data are shown to be compatible with that set of expressions in which drag is due primarily to skin friction rather than form drag
Additional details
Additional titles
- Augmented title (English)
- PWR; BWR
Publishing Information
- Imprint Title
- Proceedings of the ANS/ASME/NRC international topical meeting on nuclear reactor thermal-hydraulics: fundamental aspects of two-phase flow and boiling heat transfer
- Journal Page Range
- p. 1343-1362.
- Report number
- NUREG/CP--0014(Vol.2)
Conference
- Title
- ANS/ASME topical meeting on reactor thermal-hydraulics.
- Dates
- 9 - 12 Oct 1980.
- Place
- Saratoga, NY, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12641509
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANNULAR SPACE; BUBBLES; BWR TYPE REACTORS; FUEL ASSEMBLIES; FUEL CHANNELS; LOSS OF COOLANT; MATHEMATICAL MODELS; PWR TYPE REACTORS; REACTOR SAFETY; TWO-PHASE FLOW; VOID FRACTION
- Descriptors DEC
- ACCIDENTS; CONFIGURATION; FLUID FLOW; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS