Upcoming Grad Seminar- Dr. Scott Middlemas

(February 6th, 2019)
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Scott Middlemas

Dr. Middlemas will be speaking at Graduate Seminar on February 11th at 4:00pm. The seminar will be located in 256 CB.


About the Presenter


Dr. Scott Middlemas was born and raised in Sandy, UT, and studied metallurgical engineering at the University of Utah, receiving his B.S. in 2009. He continued his graduate studies at the U and worked with Prof. Zak Fang to develop energy-saving methods of producing titanium dioxide and titanium metal powders. In 2013, he received his Ph. D in metallurgical engineering and started a 3-year post-doctoral fellowship at the Army Research Lab in Aberdeen, Maryland. Scott has been a staff scientist at INL since 2016 and specializes in the measurement and analysis of thermal properties of both pre- and post-irradiated nuclear fuels and structural materials.



Since its first successful demonstration at the EBR-I reactor in the Southeastern Idaho desert nearly 7 decades ago, nuclear reactors have generated terawatts of carbon-free, baseload electrical power, and currently generate nearly 20% of all electricity in the United States. However, the extreme temperature and radiation environments of nuclear reactor cores continue to pose a wide variety of materials challenges. The successful continued operation of light water reactors and the development of next-generation reactors require deterministic understanding of reactor material properties, including thermophysical properties (TPPs).  TPPs define the thermal behavior of nuclear materials, especially heat generation and conduction within the fuel elements and its convective transfer to the reactor coolant system. This presentation will include a brief discussion of the theories and measurement techniques of key TPPs such as thermal conductivity, thermal diffusivity, heat capacity, and thermal expansion. The Material and Fuels Complex (MFC) at the Idaho National Laboratory (INL) features a suite of precision instruments for measuring the TPPs of both uranium-based and transuranic fuels, and the efforts to enhance its capabilities to measure post-irradiated fuel and structural materials will be presented.