In-Pile Thermal Conductivity Measurement Method for Nuclear Fuels
Description
Thermophysical properties of advanced nuclear fuels and materials during irradiation must be known prior to their use in existing, advanced, or next generation reactors. Thermal conductivity is one of the most important properties for predicting fuel and material performance. A joint Utah State University (USU)/Idaho National Laboratory (INL) project, which is being conducted with assistance from the Institute for Energy Technology at the Norway Halden Reactor Project, is investigating in-pile fuel thermal conductivity measurement methods. This paper focuses on one of these methods - a multiple thermocouple method. This two-thermocouple method uses a surrogate fuel rod with Joule heating to simulate volumetric heat generation to gain insights about in-pile detection of thermal conductivity. Preliminary results indicated that this method can measure thermal conductivity over a specific temperature range. This paper reports the thermal conductivity values obtained by this technique and compares these values with thermal property data obtained from standard thermal property measurement techniques available at INL's High Test Temperature Laboratory. Experimental results and material properties data are also compared to finite element analysis results.
Additional details
Identifiers
Publishing Information
- Imprint Pagination
- vp.
- Report number
- INL/CON--09-16451
Conference
- Title
- 30. International Thermal Conductivity Conference; 18. International Thermal Expansion Symposium
- Dates
- 29 Aug - 3 Sep 2009
- Place
- Pittsburgh, PA (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 41016941
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DETECTION; FUEL RODS; IRRADIATION; JOULE HEATING; NUCLEAR FUELS; PERFORMANCE; THERMAL CONDUCTIVITY; THERMAL EXPANSION; THERMOCOUPLES
- Descriptors DEC
- ELECTRIC HEATING; ENERGY SOURCES; EXPANSION; FUEL ELEMENTS; FUELS; HEATING; MATERIALS; MEASURING INSTRUMENTS; PHYSICAL PROPERTIES; PLASMA HEATING; REACTOR COMPONENTS; REACTOR MATERIALS; THERMODYNAMIC PROPERTIES
Optional Information
- Contract/Grant/Project number
- AC07-05ID14517
- Funding organization
- US Department of Energy (United States)