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Pradip Kumar Saha

Observed names: P Saha, P. Saha, P. Sáha, Pradip Saha, Saha, P, Saha, P., Saha, Pradip
Institution: Hitachi (Japan)
Observed institutions: United States Nuclear Regulatory Commission, Georgia Institute of Technology, General Electric (United States), Brookhaven National Laboratory, Massachusetts Institute of Technology, Hitachi (Japan)
ORCID: 0000-0001-8453-5659
Observed ORCIDs: 0000-0001-8453-5659, 0000-0002-6827-4708, 0000-0001-9240-4608
OpenAlex ID: A5101934675
Point of Net Vapor Generation and Vapor Void Fraction in Subcooled Boiling
1974 · P. Saha, Novak Zuber · International Heat Transfer Conference (IHTC) · 403
An Experimental Investigation of the Thermally Induced Flow Oscillations in Two-Phase Systems
1976 · P. Saha, M. Ishii, et al. · ASME Journal of Heat and Mass Transfer · 161
Numerical analysis of thermal striping induced high cycle thermal fatigue in a mixing tee
2008 · Jeong Ik Lee, Lin-wen Hu, et al. · Nuclear Engineering and Design · 100
An analytical study of the thermally induced two-phase flow instabilities including the effect of thermal non-equilibrium
1978 · P. Saha, N. Zuber · International Journal of Heat and Mass Transfer · 96
Issues and future direction of thermal-hydraulics research and development in nuclear power reactors
2013 · P. Saha, N. Aksan, et al. · Nuclear Engineering and Design · 50
Deteriorated turbulent heat transfer (DTHT) of gas up-flow in a circular tube: Experimental data
2008 · J.I. Lee, P. Hejzlar, et al. · International Journal of Heat and Mass Transfer · 44
A nonequilibrium heat transfer model for dispersed droplet post-dryout regime
1980 · Pradip Saha · International Journal of Heat and Mass Transfer · 42
Hot-Channel Stability of Supercritical Water-Cooled Reactors—I: Steady-State and Sliding Pressure Startup
2007 · Jiyun Zhao, Pradip Saha, et al. · Nuclear Technology · 37
High Performance Fuel Design for Next Generation PWRs: Final Report
2006 · Mujid S. Kazimi, Pavel Hejzlar, et al. · DSpace@MIT (Massachusetts Institute of Technology) · 37
Stability Analysis of Supercritical Water Cooled Reactors
2005 · Jialin Zhao, Pradip Kumar Saha, et al. · DSpace@MIT (Massachusetts Institute of Technology) · 35
Safety Analysis of High-Power-Density Annular Fuel for PWRs
2007 · Dandong Feng, Paolo Morra, et al. · Nuclear Technology · 27
Study of nonequilibrium flashing of water in a converging-diverging nozzle. Volume 2. Modeling
1981 · B.J.C. Wu, N. Abuaf, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 27
Study of nonequilibrium flashing of water in a converging-diverging nozzle. Volume 1: experimental
1981 · N. Abuaf, B.J.C. Wu, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 25
A Nonequilibrium Vapor Generation Model for Flashing Flows
1984 · P. Saha, N. Abuaf, et al. · ASME Journal of Heat and Mass Transfer · 24
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Deteriorated turbulent heat transfer (DTHT) of gas up-flow in a circular tube: Heat transfer correlations
2008 · J.I. Lee, P. Hejzlar, et al. · International Journal of Heat and Mass Transfer · 23
A Review of Two-Phase Steam-Water Critical Flow Models with Emphasis on Thermal Nonequilibrium
1978 · USDOE, Pradip Saha, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 20
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Nuclear Reactor Safety Analysis
2017 · Saha, Pradip · ASME Press eBooks · 19
Core-Wide (In-Phase) Stability of Supercritical Water-Cooled Reactors—I: Sensitivity to Design and Operating Conditions
2008 · Jiyun Zhao, Pradip Saha, et al. · Nuclear Technology · 19
Hot-Channel Stability of Supercritical Water-Cooled Reactors—II: Effect of Water Rod Heating and Comparison with BWR Stability
2007 · Jiyun Zhao, Pradip Saha, et al. · Nuclear Technology · 18
Applicability of small-scale integral test data to the 4500MWt ESBWR loss-of-coolant accidents
2009 · Pradip Saha, Robert E. Gamble, et al. · Nuclear Engineering and Design · 17
Coupled Neutronic and Thermal-Hydraulic Out-of-Phase Stability of Supercritical Water-Cooled Reactors
2008 · Jiyun Zhao, Pradip Saha, et al. · Nuclear Technology · 16
Studies of the deteriorated turbulent heat transfer regime for the gas-cooled fast reactor decay heat removal system
2007 · Jeong Ik Lee, Pavel Hejzlar, et al. · Nuclear Engineering and Design · 16
Core-Wide (In-Phase) Stability of Supercritical Water-Cooled Reactors—II: Comparison with Boiling Water Reactors
2008 · Jiyun Zhao, Pradip Saha, et al. · Nuclear Technology · 15
Analysis of a Convection Loop for GFR Post-LOCA Decay Heat Removal
2004 · Wesley C. Williams, Pavel Hejzlar, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 14
Non-equilibrium aspects of water reactor safety
1977 · O.C. Jones, P. Sáha · University of North Texas Digital Library (University of North Texas) · 14
Works count: 78
Citation count: 1,355
H-index: 18
I10-index: 25
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