Subchannel Thermal Hydraulic Experimental Program (STEP). Volume 2. Void fraction by gamma scattering. Final report. [PWR]

Technical Report · Fri Aug 01 04:00:00 EDT 1980

DOI:https://doi.org/10.2172/5136972· OSTI ID:5136972

Zielke, L. A.; Grant, K. W.; MacKinnon, J. G.

This volume provides a description of the gamma-scattering technique for the measurement of local void fraction within complex geometries. The technique was applied to measurements in the center subchannel of a 4 x 4 array of electrically heated rods with four heated walls. Over 300 data points were obtained covering thermal-hydraulic conditions typical of light water reactors. Results indicate a large variation of void fraction within the center subchannel and a measured-average void fraction higher than predicted by the COBRA IV computer code.

• Research Organization: Babcock and Wilcox Co., Alliance, OH (USA). Research Center
• OSTI ID: 5136972
• Report Number(s): EPRI-NP-1493(Vol.2)
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ENERGY TRANSFER
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL RODS
GAMMA RADIOGRAPHY
HEAT TRANSFER
HYDRAULICS
INDUSTRIAL RADIOGRAPHY
MECHANICS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
TEST FACILITIES
VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS