Ex-reactor determination of thermal gap and contact conductance between uranium dioxide: zircaloy-4 interfaces. Stage I: low gas pressure. [PWR; BWR]
A study of thermal gap and contact conductance between depleted uranium dioxide (UO/sub 2/) and Zircaloy-4 (Zr4) has been made utilizing two measurement apparatuses developed as part of this program. The Modified Pulse Design (MPD) apparatus is a transient technique employing a heat pulse (laser) and a signal detector to monitor the thermal energy transmitted through a UO/sub 2//Zr4 sample pair which are either physically separated or in contact. The Modified Longitudinal Design (MLD) apparatus is a steady-state technique based on a modified cylindrical column design with a self-guarding sample geometry. Description of the MPD and MLD apparatus, data acquisition, reduction and error analysis is presented along with information on specimen preparation, thermal property and surface characterization. A technique using an optical height gauge to determine the average mean-plane of separation between the simple pairs is also presented.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, WA (USA)
- DOE Contract Number:
- EY-76-C-06-1830
- OSTI ID:
- 6268967
- Report Number(s):
- NUREG/CR-0330; PNL-2696
- Country of Publication:
- United States
- Language:
- English
Similar Records
Ex-reactor determination of thermal gap conductance between uranium dioxide--Zircaloy-4 interfaces. [BWR; PWR]
Ex-Reactor Determination of Thermal Gap Conductance Between Uranium Dioxide and Zircaloy-4: Stage II: High Gas Pressure
Ex-reactor determination of thermal gap conductance between uranium dioxide and Zircaloy-4. Stage II: high gas pressure
Conference
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Mon Aug 01 00:00:00 EDT 1977
·
OSTI ID:6650643
Ex-Reactor Determination of Thermal Gap Conductance Between Uranium Dioxide and Zircaloy-4: Stage II: High Gas Pressure
Technical Report
·
Tue Jul 01 00:00:00 EDT 1980
·
OSTI ID:1076471
Ex-reactor determination of thermal gap conductance between uranium dioxide and Zircaloy-4. Stage II: high gas pressure
Conference
·
Fri May 01 00:00:00 EDT 1981
·
OSTI ID:6029459
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
ACTINIDE COMPOUNDS
ALLOYS
BWR TYPE REACTORS
CHALCOGENIDES
ENERGY TRANSFER
FUEL CANS
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
OXIDES
OXYGEN COMPOUNDS
PHYSICAL PROPERTIES
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACTINIDE COMPOUNDS
ALLOYS
BWR TYPE REACTORS
CHALCOGENIDES
ENERGY TRANSFER
FUEL CANS
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
OXIDES
OXYGEN COMPOUNDS
PHYSICAL PROPERTIES
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS