Douglas Miller

Associate Teaching Professor, Engineering
Program Coordinator, Mechanical Engineering Technology
Research Associate, Mechanical and Nuclear Engineering
Faculty Advisor, Faculty Advisors
DEF Building, Room 110K
Penn State DuBois
1 College Place
DuBois PA 15801

Born and raised in Schuylkill county, Pennsylvania, Dr. Miller grew up following Penn State sports and found himself interested in pursuing an Engineering degree beginning his initial years of study at Penn State Schuylkill.  He was granted admission to the Schreyer Honor College in addition to his pursuit of the Engineering Science degree and added an academic minor in Engineering Mechanics. 

Following his undergraduate degree, Dr. Miller then pursued his masters and doctoral degrees in Nuclear Engineering with research focused on the Nuclear Thermal-hydraulics of Reactors and Reactor Safety with interest in past nuclear accidents at Three Mile Island, Chernobyl, and Fukushima which present unique events which must be studied in order to prevent similar events in the future.


When not working, Dr. Miller enjoys spending time with his fiancee, Melissa and his dogs, Sweet pea and Honey Bun.

Energy Systems

Nuclear Power

Thermal / Fluid Science

Multi-phase Heat Transfer

Nuclear Reactor Thermal Hydraulics

Nuclear Safety

D. J. Miller, F. B. Cheung, and S. M. Bajorek, "Investigation of Grid-Enhanced Two-Phase Convective Heat Transfer in the Dispersed Flow Film Boiling Regime" Paper No. 127, Proceedings of 9th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-9), Kaohsiung City, Taiwan, September 2012.

D. J. Miller, F. B. Cheung and S. M. Bajorek, "On the Development of a Grid-Enhanced Single-Phase Convective Heat Transfer Correlations," Nuclear Engineering and Design, Vol. 264, pp. 56-60, 2013.

D. J. Miller, F. B. Cheung, and S. M. Bajorek, "Investigation of Grid-Enhanced Two-Phase Convective Heat Transfer in the Dispersed Flow Film Boiling Regime," Nuclear Engineering & Design, Vol. 265, pp. 35-44. 2013.

L. E. Hochreiter, F.B. Cheung, T. Lin, D. J. Miller, B. R. Lowery, “Rod Bundle Heat Transfer Facility Steam Cooling with Droplet Injection Experiments Data Report,” NUREG/CR-7192 Volume 1, U.S. NRC, May 2015.

L. E. Hochreiter, F.B. Cheung, T. Lin, D. J. Miller, B. R. Lowery, “Rod Bundle Heat Transfer Facility Steam Cooling with Droplet Injection Experiments Data Report,” NUREG/CR-7192 Volume 2, U.S. NRC, May 2015.

M. P. Riley, L. Mohanta, D. J. Miller, F. B. Cheung, S. M. Bajorek, K. Tien, & C. L. Hoxie, "Subchannel Analysis and Correlation of RBHT Steam Cooling Data," Proceedings International Seminar on Subchannel Modeling, CFD, and CHF (ISACC-2015), Shenzhen, China, December 2015.

L. E. Hochreiter, F.B. Cheung, T. Lin, D. J. Miller, B. R. Lowery, “Rod Bundle Heat Transfer Facility Two-Phase Mixture Level Swell and Uncovery Experiments Data Report,” NUREG/CR-7218 Volume 1, U.S. NRC, September 2016.

L. E. Hochreiter, F.B. Cheung, T. Lin, D. J. Miller, B. R. Lowery, “Rod Bundle Heat Transfer Facility Two-Phase Mixture Level Swell and Uncovery Experiments Data Report,” NUREG/CR-7218 Volume 2, U.S. NRC, September 2016.

M. P. Riley, L. Mohanta, D. J. Miller, F. B. Cheung, S. M. Bajorek, K. Tien, & C. L. Hoxie, "Subchannel Analysis and Correlation of the Rod Bundle Heat Transfer (RBHT) Steam Cooling Experimental Data,” KERNTECHNIK Journal, 81, 2016.

Y. Jin, L. Mohanta, F. R. Beck, D. J. Miller, F. B. Cheung, S. M. Bajorek, K. Tien and C. L. Hoxie, 2017, "Investigation of two-phase flow mixture pressure drop across a spacer grid in Dispersed Flow Film Boing (DFFB) regime", Proceedings of 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 2017.

H. T. Kumru, Y. Jin, F. R. Beck, D. J. Miller, F. B. Cheung, S. M. Bajorek, K. Tien, C. L. Hoxie and L. Mohanta, 2017, " Effects of Pressure, Subcooling and the Spacer Grid on the Minimum Film Boiling Temperature Under High Flooding Rate Conditions", Proceedings of 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 2017.

F. R. Beck, Y. Jin, L. Mohanta, S. Qiao, A. J. Rau, D. J. Miller, F. B. Cheung, B. R. Lowery, S. M. Bajorek, K. Tien and C. L. Hoxie, 2017, " Effects of Period and Flow Rate on Liquid Entrainment and the Droplet Field Under Forced Oscillatory Reflood Conditions", Proceedings of 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, China, September 2017.

Y. Jin, D.J. Miller, S. Qiao, S. J. Kim, Fan-Bill B Cheung, S. M. Bajorek, K. Tien and C. L. Hoxie, 2018, "Uncertainty Analysis on Droplet Size Measurement in Dispersed Flow Film Boiling Regime during Reflood Using Image Processing Technique", Nuclear Engineering and Design, 326

Y. Jin, F.R. Beck, B.R. Lowery, D.J. Miller, Fan-Bill B Cheung, S. M. Bajorek, K. Tien and C. L. Hoxie, 2018, "Experimental Study of Droplet Sizes across a Spacer Grid Location under Various Reflood Conditions", Experimental Thermal and Fluid Sciences, 94

BS, Engineering Science, Minor, Engineering Mechanics - Penn State

MS, Nuclear Engineering - Penn State

PhD, Nuclear Engineering - Penn State