Research Areas: High Temperature Test Laboratory
Biography: Kurt Davis has over twenty eight years of experience with tangible proficiency in sensor development and fabrication, X-ray system design and operation, high temperature testing, nuclear material handling and thermal modeling. His most recent contributions include a diamond temperature sensor and fuel pin diameter gauge for real-time data collection during in-pile irradiation testing. Other highlights include being a NASA product improvement team leader for the Space Shuttle and being the Principle Investigator representing INL on the Integrated Research Project for Advanced instrumentation for Transient Reactor Testing.
B.S., Mechanical Engineering - Utah State University
Peer-Reviewed PublicationsK. L. Davis, D. L. Knudson, J. L. Rempe, J. C. Crepeau and S. Solstad, “Design and Laboratory Evaluation of Future Elongation and Diameter Measurements at the Advanced Test Reactor,” Nuclear Technology, Volume 191, July 2015, pp 92 - 105.
J. Rempe, D. Knudson, J. Daw, T. Unruh, B. Chase, and K. Davis, “Enhanced In-pile Instrumentationat the Advanced Test Reactor,” invited paper for ANIMMA 2011 Special Edition, IEEE Transactionson Nuclear Science,59, Issue 4, Part:2, August 2012, pp 1214 -1223.
Conference PapersTong June Kim, Kurt Davis, Mark H. Anderson and Michael Corradini, “High Temperature Radiation Resistant Diamond Temperature Sensor.” Transactions of the American Nuclear Society, Advanced Measurement Techniques, Vol. 117, pp. 538-540, November 2017.
Richard Skifton, Kurt Davis, John Crepeau and Steinar Solstad, “In-pile Measurements of Fuel RodDimensional Changes Utilizing the Test Reactor Loop Pressure for Motion, 10th InternationalTopical Meeting on Nuclear Plant Instrumentation, Control, and Human Machine InterfaceTechnologies (NPIC&HMIT 2017), San Francisco, CA, June 11-15, 2017.
A. Joseph Palmer, Kurt L Davis, Joy L. Rempe, Sebastien P. Teysseyre, Gordon Kohse, Yakov Ostrovsky, and David M. Carpenter, “Adaptation of Crack Growth Detection Techniques to US Material Test Reactors,” Proceedings of the 2014 International Conference on Advances in Nuclear Power Plants ( ICAPP 2014), Charlotte, USA, April 6-9, 2014.
J. L. Rempe, D. L. Knudson, J. E. Daw, T. Unruh, B.M. Chase, K. Davis, A. J. Palmer, and R. S. Schley, "Advanced In-pile Instrumentation for Materials Testing Reactors," 2013 Conference on Advancements in Nuclear Instrumentation, Measurements Methods (ANIMMA 2013), June 23-27, 2013, Marseilles, France.
J. Rempe, D. Knudson, J. Daw, T. Unruh, B. Chase, K. Davis, and R. Schley, “Enhanced Instrumentation for Materials and Test Reactors,” 8th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human Machine Interface Technologies (NPIC&HMIT 2012), San Diego, CA, July 22-26, 2012.
K. L. Davis, B . Chase, T. Unruh, D. Knudson, J. Rempe, H. Chichester, K. Sridharan, "Use of Silicon Carbide Monitors in ATR Irradiation Testing," 8th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human Machine Interface Technologies (NPIC&HMIT 2012), San Diego, CA, July 22-26, 2012.
K. L. Davis, D.L. Knudson, J.E. Daw, J.L. Rempe and A.J. Palmer, "Melt Wire Sensors Available to Determine Peak Temperatures in ATR Irradiation Testing," 8th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human Machine Interface Technologies (NPIC&HMIT 2012), San Diego, CA, July 22-26, 2012.
J. Rempe, K. Davis, et. al., “Enhanced In-pile Instrumentation at the Advanced Test Reactor,” Proceedings of the Second International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA2011), Ghent, Belgium, June 2011.
K. L. Davis and C. J. Stanley, “Application of Real-Time Radioscopy and Digital Imaging to the Examination of Transuranic (TRU) Waste at the Idaho National Engineering and Environmental Laboratory (INEEL),” Nuclear Waste Instrumentation Engineering, Society of Photo-Optical Instrumentation, Volume 3536, Boston, Massachusetts, November 1998.
L. J. Siefken, C. M. Allison, K. L. Davis, and J. K. Hohorst, “Oxidation During Reflood of Reactor Core with Melting Cladding,” Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7, NUREG/CP-0142, Vol. 2 pp. 1851 – 1862, Saratoga Springs, New York, September 1995.