Keegan D. Murray

Keegan D. Murray.

Keegan D. Murray

Postdoctoral Scholar
Organizations
Nuclear Science and Engineering
Address

E104 Radiation Center
Corvallis, OR 97331
United States

Degrees
Ph.D. Mechanical Engineering, University of Wisconsin-Madison (2025)
B.S. Mechanical Engineering, Marquette University (2019)
Biography

Keegan D. Murray is a Postdoctoral Scholar in the School of Nuclear Science and Engineering in the Thermal-Hydraulics Group starting in fall of 2025 researching multiphase flow and reactor thermal-hydraulics phenomena. Keegan received his Ph.D. in Mechanical Engineering from the University of Wisconsin-Madison in August 2025, under Professor Mark H. Anderson. Prior to his graduate studies, he received his B.S. in Mechanical Engineering from Marquette University in 2019. Keegan gained industry experience as a Nuclear System Engineer II at Davis-Besse Nuclear Power Station, where he was responsible for the long-term system performance monitoring and maintenance strategy for the Emergency Core Cooling Systems and the Reactor Coolant Chemical and Volume Control System and was involved in refueling outage inspections.

His research involves the study and experimental investigation of multiphase flow phenomena, developing and applying advanced experimental techniques to enhance the understanding of complex thermal-hydraulic phenomena in light water reactor systems. This includes utilizing advanced instrumentation techniques, including fiber optical temperature sensors to analyze fuel cladding temperature profiles under various prototypical and accident conditions. His work includes experimentation on Accident Tolerant Fuel (ATF) cladding candidates during Critical Heat Flux (CHF) events, examining post-CHF heat transfer, rewetting phenomena, Loss of Coolant Accident reflood behavior, and transient CHF behavior. 

Awards/Accolades
High resolution experimental analysis of reflood quenching during prototypical PWR LOCA events (2025)
High Resolution Temperature Measurements during a LOCA Reflood Event (2024)
Fuel Rod Time at Post-CHF Temperature Development for PWR and BWRs (2024)
Time in DNB experimental study on Cr coated zircaloy cladding (2024)
Experimental assessment of the rewetting phenomenon after CHF under prototypical LWR conditions (2023)
Assessment of the Rewetting Phenomenon After DNB Events Under Prototypical PWR Conditions (2023)