Dr. Arjun Pradeep, Indira Gandhi Centre for Atomic Research, India
Dr. Arjun Pradeep π¨βπ¬ is a Scientific OfficerβF at IGCAR, Kalpakkam, and an M.Tech guide at Homi Bhabha National Institute π. His research spans nuclear safety, hydrogen production, and sodium fire mitigation π₯. With award-winning publications π
, CFD expertise π», and leadership at the Indian Sodium School π, he has significantly advanced SFR technologies. A GATE qualifier and INS life member, Dr. Pradeep combines innovation, mentorship, and applied science to serve India’s nuclear mission .
Profile
SCOPUS ID
π Early Academic Pursuits
Dr. Arjun Pradeep embarked on his academic journey with a B.Tech in Chemical Engineering from TKM College of Engineering, University of Kerala. He further pursued M.Tech in Chemical Engineering with a specialization in Fast Breeder Reactor and Recycle Science and Technology at the prestigious Homi Bhabha National Institute, Mumbai, under the mentorship of Prof. P. Chellapandi. Driven by a deep interest in nuclear thermal systems, he earned his Ph.D. in Engineering under Prof. Anil Kumar Sharma, focusing on mass transfer from rising mixed gas bubbles in a quiescent liquid pool of sodium-cooled fast reactors.
πΌ Professional Endeavors
Since 2008, Dr. Pradeep has served at the Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam, contributing to India’s nuclear R&D landscape. As Scientific Officer β F, he leads the Safety Engineering Division and mentors postgraduate scholars as an M.Tech guide for the Homi Bhabha National Institute. His work spans sodium waste disposal, fire suppression, and nuclear hydrogen production. He also plays a pivotal role in the Indian Sodium School as a course coordinator and instructor. π¬
π¬ Contributions and Research Focus On Chemical Engineering
Dr. Pradeepβs core research focuses on numerical simulation of turbulent natural convection, bubble dynamics, and aerosol behavior in nuclear systems. His pioneering work includes sodium pool scrubbing for iodine retention, sodium fire extinguisher development, and clean hydrogen production via copper-chlorine cycles. He integrates CFD models with experimental validations, ensuring robust safety designs in fast breeder reactor technology. π§―π¨
π Impact and Influence
Dr. Pradeep has shaped India’s scientific and safety framework for sodium-cooled reactors. His contributions have led to improved aerosol removal strategies, efficient containment systems, and innovations in hydrogen production. As a member of the task force on hydrogen production at FBTR/IGCAR, he is actively driving India’s clean energy mission. His academic influence extends through teaching advanced heat transfer and training professionals in decommissioning sodium facilities. π
π§ Research Skills
Dr. Pradeep is proficient in programming languages like C++ and Fortran and well-versed in simulation tools such as Fluent, OpenFOAM, Matlab, and COMSOL. His experimental expertise spans sodium disposal, aerosol scrubbing, and bubble dynamics, blending empirical design with advanced computational models. He is also skilled in guiding postgraduate research, as evident in his mentorship of M.Tech students working on molten salt pyroprocessing. π»π§ͺ
π
Awards and Honors
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π₯ Group Achievement Award (2014) by the Department of Atomic Energy for safety demonstrations in sodium systems.
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π Best Paper Award (2019) at the 7th Asian Symposium on Computational Heat Transfer and Fluid Flow, Tokyo.
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π GATE Qualified (2007) for postgraduate studies with fellowship in Chemical Engineering.
ποΈ Legacy and Future Contributions
Dr. Arjun Pradeep stands as a leading figure in Indiaβs atomic energy sector, bridging academic insight with applied nuclear safety engineering. His legacy is enriched by his contributions to reactor safety systems, clean energy solutions, and capacity building through education. In the coming years, he is expected to pioneer further advancements in hydrogen technology, sodium science, and sustainable reactor designs, ensuring a safer and greener nuclear future for India. βοΈπ±
Publications Top Notes
π Annals of Nuclear Energy
1οΈβ£ Interaction of natural convection flow in multiple open cavities formed due to horizontal fins
π
2011
π Nuclear Engineering and Design
2οΈβ£ Estimation of retention factor of cesium in sodium pool under fuel pin failure scenario in SFR
π
2012
π Progress in Nuclear Energy
3οΈβ£ Estimation of radionuclide transport to reactor containment building under unprotected severe accident scenario in SFR
π
2014
π Annals of Nuclear Energy
4οΈβ£ Estimation of evaporation rate of cesium from hot sodium pool to inert cover gas of typical SFR
π
2016
π Nuclear Engineering and Technology
5οΈβ£ Semiempirical model for wet scrubbing of bubble rising in liquid pool of sodium-cooled fast reactor
π
2018
π SΔdhanΔ β Journal of the Indian Academy of Sciences
6οΈβ£ Numerical investigation of single bubble dynamics in liquid sodium pool
π
2019
π Brazilian Journal of Chemical Engineering
7οΈβ£ Numerical and experimental investigation of air-water system to simulate bubble dynamics in liquid sodium pool
π
2020
π Progress in Nuclear Energy
8οΈβ£ Experimental and numerical investigation of aerosol penetration through submerged gravel bed scrubber
π
2024