Timothy M. Schriener

Research Associate Professor

Research Topics: Nuclear reactor simulation, Computational Fluid Dynamics, Space nuclear power, Dynamic system simulation

Institute for Space and Nuclear Power Studies
MSC01-1120
1 University of New Mexico
Albuquerque, NM 87131-0001
Phone: 505.272.7156
Email: schrient@unm.edu

Education

• Ph.D. Engineering, University of New Mexico, 2015
• B.S Nuclear Engineering, Oregon State University 2006

Dr. Timothy Schriener is an Research Associate Professor with the Institute for Space and Nuclear Power Studies (UNM-ISNPS) and University of New Mexico's Department of Nuclear Engineering. He has 18 years of experience performing research on engineering design and modeling and simulation for nuclear power systems in the areas of reactor neutronics and fuel depletion analyses, space nuclear power, radiation shielding and dose rate analysis, thermal-hydraulics and numerical heat transfer, computational fluid dynamics, liquid metals heat transfer, dynamic modeling of reactor power systems, thermal modeling of radioisotope power systems, and simulating digital control systems for nuclear plant cybersecurity analysis. Dr. Schriener has authored and co-authored 26 referred journal papers and 25 conference full papers, as well as 13 technical reports to DOE and NASA, and is an inventor on 4 patent disclosures. He is currently a Co-PI on multiple funded awards. These include a DOE Nuclear Engineering University Program (NEUP) project with Purdue University investigating the development and application of AI and ML methods to the autonomous control of microreactors, a NASA Early Stages Innovation grant to develop an innovative lightweight heat pipe radiator panel concept for waste heat rejection of nuclear reactor systems for space exploration and lunar surface power, and a DOE Integrated Research Project (IRP) with City College of New York, Purdue University and Argonne National Laboratory to develop and investigate advanced computational fluid dynamics capabilities for thermal-hydraulics and safety analyses of advanced GEN-IV sodium fast reactors and very high temperature helium cooled reactors.

* Member: American Nuclear Society (ANS) 2002-2023

* Member: American Institute of Aeronautics and Astronautics (AIAA) 2023

* Recipient: ChNE Outstanding Graduate Student Award 2012, 2015

* Recipient: General Ernest C. Hardin Scholarship Award Recipient 2008