In-Pile Thermal Conductivity Measurement Method for Nuclear Fuels

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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 ... continued below

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Rempe, Joy L.; Fox, Brandon; Ban, Heng; Daw, Joshua E.; Knudson, Darrell L. & Condie, Keith G. August 1, 2009.

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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.

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  • 30th International Thermal Conductivity Conference and the 18th International Thermal Expansion Symp,Pittsburgh, PA,08/29/2009,09/03/2009

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  • Report No.: INL/CON-09-16451
  • Grant Number: DE-AC07-05ID14517
  • Office of Scientific & Technical Information Report Number: 968571
  • Archival Resource Key: ark:/67531/metadc926400

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  • August 1, 2009

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  • Nov. 13, 2016, 7:26 p.m.

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  • Dec. 7, 2016, 3:33 p.m.

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Rempe, Joy L.; Fox, Brandon; Ban, Heng; Daw, Joshua E.; Knudson, Darrell L. & Condie, Keith G. In-Pile Thermal Conductivity Measurement Method for Nuclear Fuels, article, August 1, 2009; [Idaho]. (digital.library.unt.edu/ark:/67531/metadc926400/: accessed June 17, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.