Researcher

Palash Bhowmik

Post-doctoral research associate

Research Areas:
Advanced Energy Systems; Advanced Reactor Technology High Temperature Gas Cooled Reactor Simulation Methods; Cross-disciplinary applications; Experimental design; Neutron/ion irradiation damage of nuclear materials; Nuclear Engineering; Radiation Tolerant Materials; University Partnerships

Biography:

Palash Kumar Bhowmik is a post-doctoral research associate in the Irradiation Experiment Thermal Hydraulics Analysis department, Reactor System Design and Analysis Division of Idaho National Laboratory. His research contribution covers the technical areas of nuclear system design, analysis, and model development for irradiation experiments, thermal-hydraulics system code analysis, multi-physics simulations, modeling, and validations. His academic background includes bachelor's in electrical and electronics engineering, master's and Ph.D. in nuclear engineering, and MBA. His doctoral research on scaling, experiments, and simulations of condensation heat transfer for advanced nuclear reactor's safety.

The track record of Mr. Bhowmik demonstrates a successful career in the industry and research. He has industry experiences with proven management skills in power plant, nuclear research reactor (TRIGA MARK-II), and oil refinery. His previous roles include serving as the president of the graduate student council.

Among his scholarly contributions are 15+ publications in SCI journals, 15+ Conference papers, 45+ verified reviews from 22+ distinguished journals, and several invited talks. His research theme is ATOMS (Advanced Thermo-nuclear Operation Modeling and Simulations).

His research focuses on energy system application, energy storage simplification, power conversion modification, thermal-hydraulic experimentation, model numeric simulation, facility safety investigation, factory control instrumentation, and system engineering computation. He holds affiliations with the Institute of Electrical and Electronics Engineers (IEEE), the American Society of Mechanical Engineers, and the American Society of Nuclear Engineers (ANS).

Digital Profiles:

OrcID

Google Scholar

Web of Science

Website

Education:

Missouri University of Science and Technology, doctor of philosophy in nuclear engineering and radiation science

Seoul National University, master of science in nuclear engineering

Chittagong University of Engineering and Technology, bachelor of science in electrical and electronic engineering

Affiliations:

American Nuclear Society
American Society of Mechanical Engineers
Institute of Electrical and Electronics Engineers

Publications:

Selected publications (for an updated list, please visit Google Scholar or OrcID links)

P.K. Bhowmik, J. A. Shamim, C. Xiangyi, K.Y. Suh*, (2020). Rod bundle thermal-hydraulics experiment with water and water-Al₂O₃ nanofluid for small modular reactor, Annals of Nuclear Energy. Vol. 150 (107870), 2021. https://doi.org/10.1016/j.anucene.2020.107870

P.K. Bhowmik, J. P. Schlegel*, et al., (2021). CFD validation of condensation heat transfer in scaled down small modular reactor applications. Part 1: pure steam, Experimental and Computational Multiphase Flow, 2021. https://doi.org/10.1007/s42757-021-0115-5

P.K. Bhowmik, J. P. Schlegel*, et al., (2021). CFD validation of condensation heat transfer in scaled down small modular reactor applications. Part 2: steam with non-condensable gas, Experimental and Computational Multiphase Flow, 2021. https://doi.org/10.1007/s42757-021-0113-7

P.K. Bhowmik, J. P. Schlegel*, et al., (2021). Design of condensation heat transfer experiment to evaluate scaling distortion in small modular reactor safety analysis, ASME Journal of Nuclear Engineering and Radiation Science, 7(3): 031406 (11 pages), NERS-20-1021, 2021. https://doi.org/10.1115/1.4050211

P.K. Bhowmik, K. Y. Suh*, et al., (2021). Flow mapping using 3D full-scale CFD simulation and hydrodynamic experiments of an ultra-supercritical turbine's combined valve for nuclear power plant, International Journal of Energy and Environmental Engineering, Springer, Vol. 12, 365–381, 2021. https://doi.org/10.1007/s40095-021-00394-0

J. A. Shamim, P.K. Bhowmik, C. Xiangyi, K.Y. Suh*, (2016). A new correlation for convective heat transfer coefficient of water–alumina nanofluid in a square array subchannel under PWR condition, Nuclear Engineering and Design. Vol. 308 (194-204), 2016. http://dx.doi.org/10.1016/j.nucengdes.2016.08.015

S.B. Alam*, P.K. Bhowmik, et al., (2019). SMR core design for civil nuclear marine propulsion using micro-heterogeneous duplex fuel. Part I: Assembly-level analysis, Nuclear Engineering and Design. Vol. 346 (157-175), May 2019. https://doi.org/10.1016/j.nucengdes.2019.03.004

S. M. Galib*, P.K. Bhowmik*, et al., (2021). A comparative study of advanced machine learning methods for automated nuclear threats detection: radioisotope identification using NaI Gamma-ray spectra, Nuclear Engineering and Technology, Vol. 53 (12), 4072-4079, 2021. https://doi.org/10.1016/j.net.2021.06.020.

F. Ahmed, P.K. Bhowmik*, et al., (2021). CFD validation with optimized mesh using benchmarking data of pebble-bed high-temperature reactor, Progress in Nuclear Energy. Vol. 134 (103653), 2021. https://doi.org/10.1016/j.pnucene.2021.103653

M. Tusar, P.K. Bhowmik, et al., (2019). Convective heat transfer and friction factor characteristics of helical strip inserted annuli at turbulent flow, International Journal of Heat and Mass Transfer, Vol. 176 (2021), 121422.

Research Interests:

Power and energy,
Radiation science
Energy storage
Instrument, control, nuclear engineering
Thermal hydraulic
Reactor systems
Design, experiment, modeling, simulations
CFD
Data science
System safety and reliability

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