Effect of spacer grids on post-CHF rod bundle heat transfer
Conference
·
OSTI ID:5920890
Rod bundle heat transfer data near spacer grids has been investigated in the Thermal Hydraulic Test Facility (THTF). Steady state, upflow film boiling tests show the grid's effect on both local surface temperatures and heat transfer coefficients.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5920890
- Report Number(s):
- CONF-811103-61; ON: TI85004527
- Country of Publication:
- United States
- Language:
- English
Similar Records
Dispersed flow film boiling heat transfer data near spacer grids in a rod bundle
Heat transfer near spacer grids in rod bundles
Two-phase pressure drop due to a spacer grid in a heated rod bundle
Journal Article
·
Mon Jan 31 23:00:00 EST 1983
· Nucl. Technol.; (United States)
·
OSTI ID:5313483
Heat transfer near spacer grids in rod bundles
Conference
·
Mon Dec 31 23:00:00 EST 1984
·
OSTI ID:5326683
Two-phase pressure drop due to a spacer grid in a heated rod bundle
Conference
·
Fri Jul 01 00:00:00 EDT 2016
·
OSTI ID:22977500
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
COOLANT LOOPS
COOLING SYSTEMS
CRITICAL HEAT FLUX
ENERGY SYSTEMS
ENERGY TRANSFER
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
FUEL ELEMENTS
FUEL RODS
HEAT FLUX
HEAT TRANSFER
REACTOR COMPONENTS
SPACERS
TEST FACILITIES
220300* -- Nuclear Reactor Technology-- Fuel Elements
COOLANT LOOPS
COOLING SYSTEMS
CRITICAL HEAT FLUX
ENERGY SYSTEMS
ENERGY TRANSFER
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
FUEL ELEMENTS
FUEL RODS
HEAT FLUX
HEAT TRANSFER
REACTOR COMPONENTS
SPACERS
TEST FACILITIES