Study of rod-bowing effect on critical heat flux. [BWR and PWR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:7136190
None
- Research Organization:
- Power Reactor and Nuclear Fuel Development Corp., Ibaraki, Japan
- OSTI ID:
- 7136190
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 24
- Country of Publication:
- United States
- Language:
- English
Similar Records
Evaluation of fuel microstructures in rods operated above critical heat flux. [BWR; PWR]
Evaluation of rod bowing effect on critical heat flux in PWR fuel assemblies
Effect of grid spacers on post-critical heat flux heat transfer. [PWR; BWR]
Conference
·
Sun Oct 31 23:00:00 EST 1976
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:7341645
Evaluation of rod bowing effect on critical heat flux in PWR fuel assemblies
Conference
·
Wed Dec 31 23:00:00 EST 1986
·
OSTI ID:5744716
Effect of grid spacers on post-critical heat flux heat transfer. [PWR; BWR]
Conference
·
Fri Jun 01 00:00:00 EDT 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5686919
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BWR TYPE REACTORS
CRITICAL HEAT FLUX
DEFORMATION
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL RODS
HEAT FLUX
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
THREE-DIMENSIONAL CALCULATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BWR TYPE REACTORS
CRITICAL HEAT FLUX
DEFORMATION
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL RODS
HEAT FLUX
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
THREE-DIMENSIONAL CALCULATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS