Published August 1980
| Version v1
Report
Voidage in a serpentine geometry nuclear boiler tube
Description
Dynamic stability threshold predictions for the once-through AGR boilers were found to be sensitive to voidage input values. Since reliable data were lacking, measurements of voidage were undertaken on a full-size serpentine boiler tube operating under representative plant conditions by use of gamma-densitometry. These measurements involved multi-chordal scanning with subsequent integration over the tube cross-section to minimize errors in mean fluid density determination. Slip ratios were computed assuming equilibrium between phases
Additional details
Publishing Information
- Imprint Title
- Proceedings of the ANS/ASME/NCR international topical meeting on nuclear reactor thermal-hydraulics: fundamental aspects of two-phase flow and boiling heat transfer
- Journal Page Range
- p. 955-969.
- 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
- 12642274
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGR TYPE REACTORS; HYDRODYNAMICS; STABILITY; STEAM GENERATORS; TWO-PHASE FLOW
- Descriptors DEC
- BOILERS; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUID MECHANICS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; MECHANICS; REACTORS; VAPOR GENERATORS