Shripad T. Revankar
Engineering · Purdue University West Lafayette
Publications
316
Citations
2,872
Est. group size
~4
Recurring co-author estimate
Active years
45
Publishing since 1981
Shripad T. Revankar works on nuclear engineering, with emphasis on molten salt reactors, thermal-hydraulics, reactor materials, and fuel cell technology. His work spans reactor design and safety analysis (including thorium-fueled and micro reactors), materials for accident-tolerant fuel cladding, and applied energy systems such as hydrogen fuel cells and electric vehicle motor drives. This breadth suggests opportunities for students interested in both fundamental nuclear reactor physics and applied energy engineering projects.
Publication output was relatively high and variable between 2017 and 2021 (peaking at 15 in 2021), followed by a gradual decline to around 7-9 papers per year in recent years (2022-2025).
Generated by claude-sonnet-5 from public bibliographic data · Jul 20, 2026
- Neutronic analysis of Th-U molten salt reactor with FLiBe salt for different materials and geometry configurations
Progress in Nuclear Energy · 2025
- Neutronic Study of Thorium-Fueled Molten Salt Reactor (TMSR) with Different Fluoride Salts
Nuclear Science and Engineering · 2025
- Self-draining bipolar plate: Experimentation with various catalyst-loading in a low temperature proton exchange membrane fuel cell
AIMS energy · 2025
- Design and Performance Analysis of Motor Drive System of Light Electric Vehicle
New Energy Exploitation and Application · 2025
- Роль сплавов FeCrAl в обеспечении радиационной стойкости и безопасности ядерных реакторов
Recent Contributions to Physics · 2025
- FEM Design and Analysis of PMBLDC Hub Motor for Electric Scooter
New Energy Exploitation and Application · 2025
- Performance and stability analysis of an electric scooter drive system
Proceedings of the Institution of Mechanical Engineers Part D Journal of Automobile Engineering · 2025
- A review of irradiation-induced hardening in FeCrAl alloy systems for accident-tolerant fuel cladding
Nuclear Engineering and Design · 2024
- Advances in technology, design and deployment of microreactors- a review
Progress in Nuclear Energy · 2024
- Effect of oxidant quantity and humidification temperature on performance of PEMFC with twin inlet and twin outlet flow field
Frontiers in Energy Research · 2024
- Elements of thermal hydraulic design of water-cooled nuclear reactors
Elsevier eBooks · 2024
- Investigating the Impact of Various Molten Salt Combinations on Reactor Criticality and Thermal Neutron Flux Distribution in SD-TMSR
2024
- Investigation on Performance of Polymer Electrolyte Membrane Fuel Cell for Different Catalyst Loadings with Novel Circular-Cavity Type Flow Field
SSRN Electronic Journal · 2024
- List of contributors
Elsevier eBooks · 2024
- Demonstration and kinetics of hydrogen loading in titanium thin films
International Journal of Hydrogen Energy · 2023
- Frontiers in Energy Research×12
- Nuclear Engineering and Design×9
- Elsevier eBooks×5
- Journal of Nuclear Engineering and Radiation Science×4
- International Journal of Heat and Mass Transfer×3
- Hitesh Bindra
Engineering · Purdue University West Lafayette
- Samuel Abiodun Olatubosun
Engineering · The Ohio State University
- Justin Thomas
Engineering · The Ohio State University
- Wenzhong Zhou
Materials Science · Purdue University West Lafayette
- Muhammad Rizki Oktavian
Engineering · Purdue University West Lafayette
This profile was generated automatically from public scholarly data (OpenAlex). Group size and activity levels are estimates derived from co-authorship patterns.
Last updated Jul 20, 2026.
Claim or correct this profile