Flow instability and flow reversal in heated annular multichannels with initial downward flow
Conference
·
OSTI ID:6551736
Experimental and theoretical results are presented regarding the stability of initial downward flow of single phase water in parallel annular channels of the Savannah River Site (SRS) fuel assembly. The test was performed on an electrically heated prototypic mockup of a Mark-22 fuel assembly. The test conditions consisted of mass fluxes, from 98--294 kg/m[sup 2]-sec, and inlet water temperatures of 25[degrees]C and 40[degrees]C. With increased power to the heaters, flow instability was detected, characterized by flow fluctuations and flow redistribution among subchannels of the outer flow channel. With increased power, a condition was observed indicating local subchannel flow reversals where certain subchannel fluid temperatures were high at the inlet and low at the exit. With additional power increased, a critical heat flux condition was observed indicating local subchannel flow reversals where certain subchannel fluid temperatures were high at the inlet and low at the exit. With additional power increases, a critical heat flux condition was reached in the outer channel.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 6551736
- Report Number(s):
- WSRC-MS-92-388; CONF-930830--2; ON: DE93006164
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
CRITICAL HEAT FLUX
ENERGY TRANSFER
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
FUEL ASSEMBLIES
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
MATHEMATICAL MODELS
MECHANICS
NATIONAL ORGANIZATIONS
PRODUCTION REACTORS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTORS
SAVANNAH RIVER PLANT
STABILITY
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
CRITICAL HEAT FLUX
ENERGY TRANSFER
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
FUEL ASSEMBLIES
HEAT FLUX
HEAT TRANSFER
HYDRAULICS
MATHEMATICAL MODELS
MECHANICS
NATIONAL ORGANIZATIONS
PRODUCTION REACTORS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTORS
SAVANNAH RIVER PLANT
STABILITY
US AEC
US DOE
US ERDA
US ORGANIZATIONS