University Subject Matter Experts List

Disclaimer: The subject matter experts listed here are provided as a resource for external developers. The information contained in these profiles is self-reported and has not been independently verified for accuracy or completeness. Listing an individual on this site does not constitute an endorsement or recommendation by the Department of Energy, Battelle Energy Alliance, LLC, or the National Reactor Innovation Center. Developers are encouraged to conduct their own due diligence when evaluating potential collaborators.

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Subject Matter Expertise	Company	Name	Link

Last Name	First Name	Institution	Subject Matter Expertise	Title	URL	Content
Couet	Adrien	University of Wisconsin-Madison	Nuclear Materials & Science	Adrien Couet	https://nric.inl.gov/expert/adrien-couet/	Dr. Adrien Couet is a Professor of Nuclear Engineering and Engineering Physics at the University of Wisconsin-Madison, where he also holds a joint appointment in Materials Science and Engineering and serves as Director of the UW Ion Beam Laboratory, a partner facility of the Nuclear Science User Facilities network. He earned his Ph.D. in Nuclear Engineering from Pennsylvania State University in 2014, building on dual bachelor's and master's degrees in Engineering Physics from Ecole Centrale de Lyon in France, and spent a year as a research engineer at Electricité de France R&D in Paris before joining UW-Madison as a faculty member in 2015. His research focuses on nuclear materials behavior in extreme environments, with particular emphasis on high-temperature and molten salt corrosion, radiation effects, plasma-facing materials for fusion applications, and the redox chemistry of advanced reactor systems. He is also a leader in applying high-throughput experimentation and machine learning to accelerate the discovery of corrosion-resistant structural materials. Dr. Couet has been recognized as a Schmidt Futures Innovation Fellow, received the Vilas Faculty Early-Career Investigator Award and the Grainger Associate Professorship at UW-Madison, and was shortlisted for the Journal of Nuclear Materials Rising Star Award. His work has appeared in high-profile journals including Nature Communications, Science Advances, the Journal of the American Chemical Society, and Acta Materialia, and spans topics from in situ molten salt corrosion monitoring to irradiation-corrosion synergies in zirconium alloys and high-entropy alloys. He also serves as Associate Chair for Graduate Studies in the NEEP department and as Technical Lead for the Nuclear Innovation Bootcamp through the Nuclear Innovation Alliance, reflecting a commitment to both departmental leadership and the broader nuclear energy ecosystem.
Khafizov	Marat	Ohio State University	Nuclear Fuel Cycle, Nuclear Materials & Science	Marat Khafizov	https://nric.inl.gov/expert/marat-khafizov/	Dr. Marat Khafizov is a Nuclear Engineering Professor at The Ohio State University with extensive expertise in nuclear fuel and materials, irradiation effects, and thermal transport. He holds a Ph.D. in Physics and has built an academic and research career spanning roles as a staff scientist at Idaho National Laboratory and faculty positions at OSU. His work focuses on understanding and modeling the behavior of irradiated nuclear fuels and materials using rate theory and cluster dynamics modeling, developing models considering impact of radiation damage on physical properties, and integrating modeling and experiment. Dr. Khafizov has secured significant research funding from the US Department of Energy, published extensively in leading nuclear and materials science journals, and contributed to the field through teaching, graduate advising, and leadership in professional societies and research initiatives.
Lindley	Ben	University of Wisconsin-Madison	Advanced Reactor Design, Computational Nuclear Engineering, Isotope Production, Nuclear Engineering, Reactor Physics, Space Nuclear Power	Ben Lindley	https://nric.inl.gov/expert/ben-lindley/	Dr. Ben Lindley is a tenure-track Assistant Professor of Nuclear Engineering and Engineering Physics at the University of Wisconsin-Madison, where he has built a research program spanning fusion technology, reactor physics, advanced reactor design, and integrated energy systems, attracting approximately $28 million in external funding since joining the faculty in 2020. He holds a Ph.D. in Engineering from the University of Cambridge, where he studied reduced-moderation light water reactors for actinide recycling, as well as a Master's degree in Mechanical Engineering from Cambridge, which he completed at the top of his class. Before moving to academia, he spent six years in industry at Jacobs in the UK, where he served as Senior Reactor Physicist and ANSWERS Technical Director, leading major R&D programs in digital reactor design, advanced reactor core physics, and radiation transport code development for the UK nuclear industry. He also holds a joint faculty appointment at Argonne National Laboratory and co-founded Realta Fusion, a UW-Madison spinout focused on fusion reactor blanket design that has raised over $50 million in funding and is an awardee of the DOE Milestone Based Fusion Development Program. Dr. Lindley's current research includes serving as principal investigator on a roughly $20 million Fusion Innovation Research Engine (FIRE) Collaborative on fusion neutron blanket technology, as well as projects on fission-fusion hybrid reactors, digital twins for tritium monitoring, nuclear process heat, and thermal energy storage. He has been named to the American Nuclear Society's inaugural 40 Under 40 list and holds four patent filings covering innovations in control rod design, actinide transmutation, reactor fuel assembly retrofits, and thermal reactor coupling with absorption chillers. He has authored or co-authored more than 50 journal papers and approximately 90 conference proceedings, and serves on the ANS Research and Advanced Reactors Consensus Committee.
Suarez	Daniel	University of Tennessee	Computational Nuclear Engineering, Nuclear Engineering, Nuclear Regulation & Policy, Nuclear Safety, Plant Operations, Reactor Physics	Daniel Suarez	https://nric.inl.gov/expert/daniel-suarez/	Dr. Daniel Suarez is a Teaching Associate Professor in the Department of Nuclear Engineering at the University of Tennessee, bringing an unusually broad background that spans nuclear power plant operations, computational fluid dynamics research, and academic instruction across three countries. He holds a Ph.D. in Nuclear Engineering and Ionizing Radiation from the Polytechnical University of Catalonia (UPC), where his dissertation — recognized with UPC's Extraordinary PhD Thesis Award in 2025 — focused on heat transfer correlations for liquid metal flows under nuclear fusion conditions using computational fluid dynamics. Before transitioning to his current academic role, he spent over a decade as a nuclear power operations instructor engineer at Tecnatom in Spain, holding the highest-level instructor certification in the Spanish nuclear industry, and subsequently served as a Postdoctoral Research Associate in the Fusion Energy Division at Oak Ridge National Laboratory, where he developed simulation tools for liquid metal magnetohydrodynamic flows in plasma-facing components and breeding blankets. Dr. Suarez's research centers on liquid metal magnetohydrodynamics for fusion thermal-hydraulic systems, with published work appearing in journals including Nuclear Science and Engineering, Fusion Engineering and Design, and Plasma Physics and Controlled Fusion. He has been a two-time recipient of the People's Choice Winner award at ORNL's Annual Research Symposium and has presented his work at major international fusion conferences including SOFT, SOFE, and ISFNT. At Tennessee, he teaches a wide range of nuclear engineering courses spanning introductory nuclear engineering through reactor theory, numerical methods, and nuclear licensing, and he brings to the classroom firsthand experience from both industrial reactor operations and cutting-edge fusion energy research.
Fritz	Dominik	Rensselaer Polytechnic Institute	Accelerator Science, Isotope Production, Nuclear Engineering, Nuclear Physics, Radiation Protection & Health Physics	Dominik Fritz	https://nric.inl.gov/expert/dominik-fritz/	Dr. Dominik Fritz is an Assistant Professor of Nuclear Engineering at Rensselaer Polytechnic Institute, where he earned both his B.S. and Ph.D. in nuclear engineering, completing his doctorate in 2022. His doctoral research focused on the design of cold moderator systems and the measurement of thermal neutron cross sections of moderator materials — work conducted in collaboration with national laboratory partners including Los Alamos and Oak Ridge — and he received a Nuclear Energy University Program fellowship to support that research. Prior to returning to RPI as faculty, he gained industry experience as a Senior Nuclear Engineer and consultant at NorthStar Medical Radioisotopes, where he contributed to radioisotope production technology including co-inventing a patented liquid deposition method for bombardment target preparation. Dr. Fritz's research sits at the intersection of neutron physics, nuclear data, and moderator materials, with a particular focus on sub-thermal neutron behavior and thermal scattering law validation. His published work includes precision cross section measurements of hydrogen-dense polymers and yttrium hydride — materials relevant to advanced reactor moderator design — conducted using the RPI Linear Accelerator (LINAC) facility. He has presented his work at leading international nuclear data conferences and collaborates with researchers across multiple national laboratories. He also completed specialized training in nuclear safeguards and nondestructive assay at Los Alamos National Laboratory through the Nuclear Science and Security Consortium.
Wilson	Paul	University of Wisconsin-Madison	Advanced Reactor Design, Computational Nuclear Engineering, Fusion Energy, Nuclear Engineering, Nuclear Fuel Cycle, Nuclear Security & Nonproliferation, Reactor Physics, Research Reactors, Waste Management	Paul Wilson	https://nric.inl.gov/expert/paul-wilson/	Paul Wilson is the Grainger Professor of Nuclear Engineering and current department chair of the University of Wisconsin-Madison‘s Department of Engineering Physics. His research interests focus on developing improved tools for computational modeling of complex nuclear energy systems, with applications in fusion technology, nuclear waste management, nuclear non-proliferation and energy policy. Paul joined the University of Wisconsin-Madison as an assistant professor in August 2001 as part of the Energy Systems and Policy Hiring Initiative. He has a PhD in Nuclear Engineering and Engineering Physics from the UW-Madison (1999) and a Dr.-Ing in Mechanical Engineering from the Karlsruhe Institute of Technology (1998). Paul was the founding President of the North American Young Generation in Nuclear [NA-YGN], and has been active in the American Nuclear Society for over 30 years, recently serving on its Board of Directors. He represented the ANS and NA-YGN at the international climate change negotiations in Buenos Aires, Argentina (1998), and Bonn, Germany (1999). Paul is married and has two daughters. They enjoy biking around Madison’s paths and rural roads, and spending time on the lakes.
Kearfott	Kimberlee	University of Michigan	Nuclear Medicine, Radiation Protection & Health Physics	Kimberlee Kearfott	https://nric.inl.gov/expert/kimberlee-kearfott/	Kim Kearfott is a board-certified radiation safety specialist at both the practitioner (NRRPT) and professional (CHP) levels. She is a tenured full Professor of Nuclear Engineering and Radiological Sciences at University of Michigan with a Doctor of Science degree from M.I.T. with a doctoral minor from Harvard School of Public Health (nuclear medicine imaging, medical physics, radiation biology). She also earned a Master of Engineering degree in Nuclear Engineering from the University of Virginia in nuclear reactor safety. Professor Kearfott received National Science Foundation Presidential Young Investigator, Society of Nuclear Medicine Tetalman, Health Physics Society Elda Anderson, and American Nuclear Society Women's Achievement and Rockwell Lifetime Achievement awards. She is a Fellow of the Health Physics Society (the primary scientific organization of radiation protection specialists in the United States) and a Distinguished Member of the American Academy of Health Physics (the board certification group for radiation protection professionals). She has served on the national board of directors of both the American Nuclear Society and the Health Physics Society. She completed training in the first class of FEMA Radiological Operations Support Specialists (ROSS). Kim Kearfott has more than four decades of research and applied experience in radiation detection and radiological safety. She began her career in reactor safety analysis. She then became known for her early work on internal dose assessments for Positron Emission Tomography (PET) and for her designs of clinical PET facilities. She performed pioneering work in radon: discovering and mitigating the highest ever recorded domestic indoor radon air concentration. She has conducted projects in the personnel radiation monitoring, external dosimetry, and internal dose assessment. Her current research is the design of radiation detection systems for environmental radiation, homeland security, and nuclear weapons verification. Dr. Kearfott maintains an interest in measurement systems of all types, including the detection of conventional explosives. She holds several patents on radiation detection methods and detectors. Dr. Kearfott has supervised ~493 graduate and undergraduate student research projects, resulting in ~601 publications. An experienced teacher, Prof. Kearfott has presented ~250 technical talks, 87 formal undergraduate and graduate courses, and 37 short courses.
Smith	Curtis	Massachusetts Institute of Technology	Advanced Reactor Design, Nuclear Engineering, Nuclear Regulation & Policy, Nuclear Safety, Risk & Reliability	Curtis Smith	https://nric.inl.gov/expert/curtis-smith/	Dr. Curtis Lee Smith is a Professor of the Practice in Nuclear Science and Engineering at MIT, holding the KEPCO endowed chair, and brings more than three decades of experience in probabilistic risk assessment to both the nuclear and aerospace industries. He holds a Ph.D. in nuclear engineering from MIT and bachelor's and master's degrees from Idaho State University, and prior to joining MIT served as Director of the Nuclear Safety and Regulatory Research Division at Idaho National Laboratory, where he led major risk-informed initiatives including the Risk-Informed Safety Margins Characterization Pathway under the DOE Light Water Reactor Sustainability Program. He is perhaps best known as the principal designer and longtime project manager of SAPHIRE, the premier probabilistic risk assessment software used by the U.S. Nuclear Regulatory Commission and NASA — a tool that has been used to analyze every operating commercial nuclear power plant in the United States as well as the Space Shuttle, the International Space Station, and NASA's Constellation Program. Beyond his software and research contributions, Dr. Smith has been one of the most prolific educators in the PRA field, personally training over 800 NRC, NASA, and DOE staff through a curriculum he largely developed himself, spanning topics from Bayesian inference to human reliability analysis. He is a Fellow of the American Nuclear Society, past President of the International Association for Probabilistic Safety Assessment and Management, and has published over 300 papers, books, and reports across his career. His work spans nuclear power plant safety, aerospace mission risk, advanced reactor licensing, and the integration of artificial intelligence and machine learning into safety analysis — making him one of the most broadly impactful figures in applied nuclear risk research today.
Biegalski	Steven	Georgia Institute of Technology	Advanced Reactor Design, Isotope Production, Nuclear Engineering, Nuclear Fuel Cycle, Nuclear Medicine, Nuclear Security & Nonproliferation, Research Reactors	Steven Biegalski	https://nric.inl.gov/expert/steven-biegalski/	Dr. Steven R. Biegalski is Chair of the Nuclear and Radiological Engineering and Medical Physics Program and Professor in the George W. Woodruff School of Mechanical Engineering at the Georgia Institute of Technology. He is internationally recognized for his expertise in advanced nuclear reactor design, reactor operations, radiation detection and environmental radioactivity, with over three decades of experience developing and deploying advanced systems for radionuclide monitoring, including β-γ coincidence spectrometry and noble gas detection for nuclear forensics and treaty verification. Dr. Biegalski currently serves in leadership roles with the American Nuclear Society (ANS) and the World Council on Isotopes (WCI), where he promotes global collaboration on isotope technology and radiation science. His contributions to nuclear measurement science have been recognized with the 2024 ANS Radiation Science and Technology Award and the 2025 Hevesy Medal, the highest international honor in radioanalytical and nuclear chemistry.
Yongfeng	Zhang	University of Wisconsin-Madison	Computational Nuclear Engineering, Nuclear Materials & Science	Zhang Yongfeng	https://nric.inl.gov/expert/zhang-yongfeng/	Dr. Yongfeng Zhang is an Associate Professor and Associate Chair for Undergraduate Studies in the Nuclear Engineering and Engineering Physics Department at the University of Wisconsin-Madison. He earned his Ph.D. in Mechanical Engineering from Rensselaer Polytechnic Institute and his undergraduate and master's degrees from the University of Science and Technology of China, before spending nearly a decade as a staff scientist and group lead at Idaho National Laboratory, where he led the Computational Microstructure Science Group. His research focuses on using computational methods to understand and design materials capable of withstanding extreme environments, with particular emphasis on the thermodynamics and kinetics of crystal defects, irradiation behavior of nuclear fuels and structural materials, fracture and plasticity, and corrosion in molten salt systems. With over 124 peer-reviewed journal publications, his work spans a wide range of materials systems relevant to both current and advanced reactor designs, including uranium fuels, TRISO particles, accident-tolerant cladding alloys, and complex concentrated alloys. Dr. Zhang is an active leader in the nuclear materials research community, serving on the TMS Nuclear Materials Committee as Vice Chair and Chair, as an executive member of the ANS Materials Science and Technology Division, and as an associate editor for Frontiers in Materials and Frontiers in Nuclear Engineering. He has led or co-led numerous funded projects through DOE's Nuclear Energy University Programs, the NRC, the Office of Science Basic Energy Sciences program, and INL's Laboratory Directed Research and Development program, covering topics ranging from reactor pressure vessel steel embrittlement to molten salt corrosion mechanisms to the mechanical behavior of TRISO fuel particle buffer layers. Recognized multiple times with INL's Exceptional Contribution Program Award and the Laboratory Director's Award for Leadership, he brings a deeply interdisciplinary perspective to materials challenges at the frontier of nuclear energy research.
Wang	Dean	Ohio State University	Advanced Reactor Design, Computational Nuclear Engineering, Nuclear Engineering, Nuclear Physics, Reactor Physics, Space Nuclear Power	Dean Wang	https://nric.inl.gov/expert/dean-wang/	Dr. Dean Wang is an Associate Professor of Nuclear Engineering at The Ohio State University, where he leads the Nuclear Computing Group within the Department of Mechanical and Aerospace Engineering. He holds a Ph.D. from MIT in reactor physics and fuel management, and master's degrees from both Purdue University and Tsinghua University, where he also completed his undergraduate studies in nuclear engineering. His research sits at the intersection of computational mathematics and nuclear engineering, with a focus on developing advanced numerical methods for neutron transport, reactor physics, thermal-hydraulics, and multiphysics coupling. Among his most notable current projects is NASA-funded work on the Centrifugal Nuclear Thermal Rocket, exploring next-generation nuclear propulsion systems capable of enabling crewed missions to Mars, alongside NRC-funded work on high-fidelity neutronics modeling for advanced reactor transient analysis. Dr. Wang brings a broad career spanning academia, national laboratory research, and regulatory support. Prior to joining Ohio State, he held faculty positions at UMass Lowell and was an R&D staff member at Oak Ridge National Laboratory, where he played a significant role in the U.S. Department of Energy's emergency response to the Fukushima Daiichi accident and contributed to foundational research on accident-tolerant fuels. He has authored or co-authored more than 30 refereed journal articles and has received multiple best paper awards from the American Nuclear Society, where he is also an active member across several technical divisions. He currently serves as General Chair of the 2027 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2027).
Bahadori	Amir	Kansas State University	Computational Nuclear Engineering, Nuclear Engineering, Nuclear Medicine, Nuclear Physics, Radiation Protection & Health Physics, Research Reactors	Amir Bahadori	https://nric.inl.gov/expert/amir-bahadori/	Amir A. Bahadori is Professor in the Alan Levin Department of Mechanical and Nuclear Engineering, serves as Nuclear Engineering Program Director, and holds the Hal and Mary Siegele Professorship in Engineering at Kansas State University. He previously worked in the Space Radiation Analysis Group at NASA’s Lyndon B. Johnson Space Center. Bahadori has an extensive background in space radiation sources and transport, radiation dosimetry, radiation detection, radiation risk models, and radiation epidemiology. He is presently collaborating on the Million Person Study of Radiation Workers and Atomic Veterans. He is a member of the American Nuclear Society, the Health Physics Society, and the Radiation Research Society. He serves on the National Council on Radiation Protection and Measurements (NCRP) and the Program Area Committee 6: Radiation Measurements and Dosimetry. In 2018, he was awarded the Zeldovich Medal for his work on space radiation detection, and in 2022, he was awarded the American Nuclear Society Presidential Citation for his work on the Society’s position statement on low-level radiation exposure health effects. Bahadori received a B.S. in mechanical engineering with nuclear engineering option and a B.S. in mathematics from Kansas State University, an M.S. in nuclear engineering sciences from the University of Florida, and a Ph.D. in biomedical engineering from the University of Florida.
Brown	Nicholas	University of Tennessee, Knoxville	Advanced Reactor Design, Computational Nuclear Engineering, Nuclear Engineering, Nuclear Fuel Cycle, Nuclear Hydrogen Production, Nuclear Materials & Science, Nuclear Regulation & Policy, Nuclear Safety, Plant Operations, Reactor Physics, Research Reactors, Waste Management	Nicholas Brown	https://nric.inl.gov/expert/nicholas-brown/	Dr. Nicholas Brown is a Full Professor of Nuclear Engineering and Pietro F. Pasqua Fellow at the University of Tennessee. Dr. Brown’s research group focuses on nuclear reactor safety, nuclear fuel safety, and nuclear reactor design. He was previously a professor at Penn State University, an R&D staff member at Oak Ridge National Laboratory, and a scientific staff member at Brookhaven National Laboratory. He has authored or co-authored more than 130 peer-reviewed journal articles, 3 book chapters, along with more than 125 total conference publications and national laboratory reports. Dr. Brown has previously served as Chair of the Nuclear Installations Safety Division of the American Nuclear Society and has served in numerous other ANS roles throughout his career. He has had more than 30 grants and contracts as a Principal or Co-Principal Investigator totaling more than $25 million in total funding, in addition to past technical leadership on several national laboratory projects. He is fundamentally dedicated to student success, creating an inclusive environment, and service. His recent honors and awards include the David Okrent Award, Landis Technical Achievement Award, and inaugural 40 under 40 from ANS and the University of Tennessee Tickle College of Engineering Professional Promise in Research Award. Dr. Brown earned his Ph.D. from Purdue University.
Sun	Xiaodong	University of Michigan	Advanced Reactor Design, Nuclear Engineering, Nuclear Safety, Space Nuclear Power	Xiaodong Sun	https://nric.inl.gov/expert/xiaodong-sun/	Dr. Xiaodong Sun is Professor of Nuclear Engineering and Radiological Sciences at the University of Michigan, where he currently serves as Interim Chair of the department and has been a faculty member since 2017. He earned dual master's degrees and a doctorate from Purdue University in nuclear and mechanical engineering, building on undergraduate and graduate training in thermal and nuclear engineering at Shanghai Jiao Tong University in China. Over a career spanning more than two decades, Dr. Sun has established himself as a leading authority in nuclear thermal-hydraulics, with research spanning post-critical heat flux heat transfer, two-phase flow dynamics, advanced heat exchanger design, and passive safety systems for next-generation reactor concepts including molten salt, fluoride salt-cooled, and high-temperature gas-cooled reactors. His experimental and computational work has been supported by the U.S. Nuclear Regulatory Commission and the Department of Energy, and he has supervised more than a dozen doctoral students and postdoctoral researchers across his time at Ohio State University and Michigan. Dr. Sun is widely recognized within the nuclear engineering community for both his research contributions and his service to the field. He is a Fellow of the American Nuclear Society and a NURETH Fellow, and has received multiple best paper awards at leading international conferences as recently as 2025, along with the ANS Thermal Hydraulics Division Technical Achievement Award and several departmental teaching and research honors from the University of Michigan. He has served in leadership roles across the ANS Thermal-Hydraulics Division — including as Division Chair — and has held technical program leadership positions at numerous international conferences on nuclear reactor thermal-hydraulics, including serving as General Co-Chair of NURETH-19. With over 110 refereed journal publications and 210 conference papers, his work continues to shape experimental methods and safety analysis frameworks for advanced reactor development.
Liu	Emily	Rensselaer Polytechnic Institute	Integrated Energy Systems, Nuclear Communications, Nuclear Education, Nuclear Engineering, Nuclear Materials & Science, Nuclear Physics, Nuclear Safety, Nuclear Security & Nonproliferation, Waste Management	Emily Liu	https://nric.inl.gov/expert/emily-liu/	Dr. Emily Liu is a Professor of Mechanical, Aerospace, and Nuclear Engineering and Industrial and Systems Engineering at Rensselaer Polytechnic Institute (RPI), where she also serves as Head of the Industrial and Systems Engineering Department and holds a joint appointment at the Lally School of Management. With a Ph.D. in Nuclear Science and Engineering from MIT and undergraduate training in Technical Physics from Peking University, she has built a career at the intersection of experimental and computational physics, bringing nearly two decades of faculty experience to bear on some of the most complex challenges in nuclear energy, materials science, and systems engineering. Her research integrates neutron scattering experiments with multiphysics simulations to illuminate fundamental questions in condensed matter physics, and her work spans topics from thermal scattering laws and small modular reactors to nuclear fuel economics and consent-based siting processes. Beyond her technical research, Dr. Liu is a recognized leader in engineering education and community engagement. She has been honored with RPI's Class of 1951 Outstanding Teaching Award and School of Engineering Education Innovation Award, and was selected as an ELATES Fellow — a prestigious program for executive leadership in academic science and engineering — at Drexel University, where she now serves as an advisor to the program. She directs RPI's STEAMM Inventor's Studio summer program, serves on multiple national advisory councils including the Partnership for Nuclear Energy Advisory Council and the Penn State Neutron Science Advisory Council, and has delivered invited talks at over 58 conferences and institutions worldwide. Her interdisciplinary approach — collaborating with economists, psychologists, and social scientists on educational research — reflects a commitment to broadening participation in STEM and advancing both the science and the culture of engineering.