Arunkumar Seshadri

Bio

Dr. Seshadri is currently a Research Scientist in the Department of Nuclear Science and Engineering at MIT. He earned both his Ph.D. and Master's degrees in Nuclear Science and Engineering from MIT, specializing in Nuclear Materials, Radiation Interactions, and Thermal Hydraulics. Additionally, he holds a joint appointment at the Idaho National Laboratory.

His primary focus is on experimental research within two research groups at MIT: the Nuclear Innovations Fission Technology group and the Center for Reactor Instrumentation and Sensor Physics. He also collaborates closely with the MIT Nuclear Reactor Lab, where he leads efforts in post-irradiation examination. Prior to his role at MIT, he served as a postdoctoral research associate at the Idaho National Laboratory.

Research

Materials for LWRs, Advanced Terrestrial and Nuclear Space Propulsion Systems

Comprehensive experimental studies at both micro and engineering scales are conducted to characterize corrosion, mechanical properties, thermophysical behavior, and thermal hydraulics of accident tolerant fuels (ATFs). In-reactor testing at MITR and CALPHAD simulations are utilized to enhance the technological readiness of ATF coatings and advanced silicon carbide composites. The development of advanced hydride moderators and high-entropy metallic and ceramic alloys are also explored, with a focus on performance in coupled radiation and high-temperature environments for next-generation reactors and space nuclear propulsion systems.

Surface Chemistry studies under Extreme Environments

The effects of ionizing radiation, high temperatures, and complex corrosive environments on the surface chemistry of various metals and alloys are investigated. Multiscale characterizations are conducted using high-resolution techniques such as TEM, SEM, XPS, EDS, and WDS to unravel intricate micro- and nanoscale interactions.

Innovating Materials Development Using Radiation

Novel techniques utilizing Co-60 and gamma irradiation are developed to create scalable micro- and nanoengineered materials. These materials exhibit enhanced heat transfer, corrosion resistance, and fouling resistance, contributing to sustainable energy applications.

Two-Phase Flows and Boiling Heat Transfer

Experimental diagnostic capabilities for two-phase flow phenomena are advanced through capacitance, optical, and acoustic imaging. Tailored experiments are performed to develop phenomenological models that account for morphological changes and surface chemistry relevant to quenching and reflooding processes in commercial light water reactors (LWRs).

Development of Sensors, Instrumentation, and Machine Learning Tools for Complex Systems

Physics-informed machine learning and advanced neural network architectures are employed to innovate instrumentation for complex experimental testing and enhance operational efficiency in nuclear power plants.

Publications

1. A. Seshadri, K. Shirvan, Development of hydrothermal corrosion model and BWR metal coating for CVD SiC in light water reactors, Journal of Nuclear Materials 576 (2023) 154252. https://doi.org/10.1016/j.jnucmat.2023.154252.
2. A. Seshadri, A.M. Jokisaari, C. Sun, A Review of Irradiation Damage and Effects in a-Uranium, Materials 15 (2022) 4106. https://doi.org/10.3390/ma15124106.
3. A. Seshadri, B. Philips, A.J. Dave, S. Harrison, J. Pegna, K. Shirvan, Hydrothermal corrosion of laser printed SiC fibers under extreme environment, Journal of Nuclear Materials 548 (2021) 152805. https://doi.org/10.1016/j.jnucmat.2021.152805.
4. A. Seshadri, B. Phillips, K. Shirvan, Impact of nuclear environment on hydrothermal corrosion and silica transport for CVD SiC in light water reactors, Journal of Nuclear Materials 556 (2021) 153155. https://doi.org/10.1016/j.jnucmat.2021.153155.
5. A. Seshadri, E.C. Forrest, K. Shirvan, Why ionizing radiation enhances surface wettability, Applied Surface Science 514 (2020) 145935. https://doi.org/10.1016/j.apsusc.2020.145935.
6. M. Sevecek, A. Gurgen, A. Seshadri, Y. Che, M. Wagih, B. Phillips, V. Champagne, K. Shirvan, Development of Cr cold spray coated fuel cladding with enhanced accident tolerance, Nuclear Engineering and Technology 50 (2018) 229-236.
7. A. Seshadri, K. Shirvan, Quenching heat transfer analysis of accident tolerant coated fuel cladding, Nuclear Engineering and Design 338 (2018) 5-15.
8. A. Seshadri, B. Phillips, K. Shirvan, Towards understanding the effects of irradiation on quenching heat transfer, International Journal of Heat and Mass Transfer 127 (2018) 1087-1095.