Greg Sinclair
About Greg Sinclair
Greg Sinclair is a Scientist III at General Atomics, specializing in the modeling of material transport in fusion devices. He has a Ph.D. in Nuclear Engineering from Purdue University and has previously worked at Purdue University and the Oak Ridge Institute for Science and Education.
Current Role at General Atomics
Greg Sinclair serves as a Scientist III at General Atomics, a position he has held since 2020. He is based in San Diego, California. In this role, he focuses on advanced research in the field of nuclear engineering, particularly in the area of fusion energy. His work involves modeling the transport of materials eroded from fusion device walls and utilizing advanced simulation tools to predict impurity transport in tokamak devices.
Previous Experience at Oak Ridge Institute
Prior to his current position, Greg Sinclair worked as a Postdoctoral Research Fellow at the Oak Ridge Institute for Science and Education from 2018 to 2020. During this two-year tenure in the Greater San Diego Area, he contributed to research projects that advanced the understanding of nuclear engineering and fusion technology, building on his extensive academic background.
Academic Background in Nuclear Engineering
Greg Sinclair completed his Doctor of Philosophy (Ph.D.) in Nuclear Engineering at Purdue University from 2014 to 2018. His research during this period focused on modeling material transport in fusion devices. He also earned a Master of Science (M.S.) in Nuclear Engineering from Purdue University from 2014 to 2017, further solidifying his expertise in the field.
Undergraduate Education in Chemical Engineering
Greg Sinclair obtained his Bachelor’s Degree in Chemical Engineering from the University of Southern California, where he studied from 2010 to 2014. This foundational education provided him with essential knowledge and skills that he applied in his subsequent studies and research in nuclear engineering.
Research Focus and Specializations
Greg Sinclair specializes in modeling the transport of materials eroded from the walls of fusion devices throughout the plasma. He utilizes the SOLPS-ITER edge plasma code package for predictive modeling of impurity transport in tokamak fusion devices. His research also investigates the viability of next-generation fusion materials, such as tungsten and silicon carbide, and he engages in proposing and executing experiments on the DIII-D tokamak to inform next-generation divertor design.