Hitesh Bindra
Engineering · Purdue University West Lafayette
Publications
118
Citations
933
Est. group size
~6
Recurring co-author estimate
Active years
21
Publishing since 2006
Hitesh Bindra works on nuclear engineering, focusing on the thermal and fluid behavior inside advanced nuclear reactors, including liquid-metal-cooled and high-temperature gas reactors. His research combines experiments (such as flow measurements using ultrasonic sensors), computer simulations, and statistical modeling to understand heat transfer, natural circulation, and safety-related transient events in reactor systems. This work supports the design and safety analysis of next-generation and small modular nuclear reactors.
Publication output has grown steadily over the last decade, rising from about 7 papers per year in 2017 to a peak of 16 in 2023, with output remaining strong (around 11-12 per year) through 2024-2025.
Generated by claude-sonnet-5 from public bibliographic data · Jul 20, 2026
- Data-driven statistical surrogates for scalar turbulence in different Prandtl numbers
SSRN Electronic Journal · 2026
- Ultrasonic Doppler velocimetry (UDV) enabled velocity field measurements in a liquid metal plenum with colder jet injection
Nuclear Engineering and Design · 2025
- Effect of stochasticity on initial transients and chaotic itinerancy for a natural circulation loop
Physical review. E · 2025
- Effects of break geometry and orientation on helium-air mixing in simulated reactor cavities of high temperature gas reactors
Nuclear Engineering and Design · 2025
- Stochastic perturbation and stability analysis of a reduced order model of natural circulation loops
International Journal of Heat and Mass Transfer · 2025
- Technoeconomic Assessment of Ammonia Production from Biomass with Nuclear Microreactors
Nuclear Technology · 2025
- Numerical simulation and experimental validation of DLOFC transients in a high temperature helium loop embedded with AM geometry
Progress in Nuclear Energy · 2025
- Experimental Analysis of Steam As Working Fluid in Direct and Indirect Heat Storage Systems
2025
- Two-Dimensional Velocity Mapping of a Liquid Metal Plenum With Colder Jet Injection via Ultrasonic Doppler Velocimetry (UDV)
2025
- Experimental Validation of CFD Models Capturing a Cold-Shock Transient in Liquid Metal Cooled Reactor Plena
2025
- Hybrid Power Block and Energy Systems for Immediate Deployment and Long-Term Nuclear Energy Integration
Transactions of the American Nuclear Society · 2025
- Experimental investigation on the Coolability of a Top Flooded Debris Bed With Seawater Injection with and without a Crust on Top
Transactions of the American Nuclear Society · 2025
- Effect of Leak in the Upper Vessel Head of HTGRs on Onset of Natural Circulation
Transactions of the American Nuclear Society · 2025
- Thermal field reconstruction and compressive sensing using proper orthogonal decomposition
Frontiers in Energy Research · 2024
- Nuclear microreactors and thermal integration with hydrogen generation processes
Nuclear Engineering and Design · 2024
- Transactions of the American Nuclear Society×18
- Annals of Nuclear Energy×8
- International Journal of Heat and Mass Transfer×6
- Elsevier eBooks×5
- Progress in Nuclear Energy×4
- Shripad T. Revankar
Engineering · Purdue University West Lafayette
- Samuel Abiodun Olatubosun
Engineering · The Ohio State University
- Justin Thomas
Engineering · The Ohio State University
- Muhammad Rizki Oktavian
Engineering · Purdue University West Lafayette
- Hany S. Abdel‐Khalik
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