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Numerical investigation on convective heat transfer in a pool with submerged heat source under seismic condition

Journal of thermal analysis and calorimetry, 2023-04, Vol.148 (7), p.2765-2779

2023

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Prediction of Vapor Film Thickness Below a Leidenfrost Drop

Journal of heat transfer, 2015-12, Vol.137 (12)

2015

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Numerical Investigation of Single-Phase Convection of Submerged Heat Exchanger under Low Frequency Excitation

Fluid Mechanics and Fluid Power (Vol. 3), 2023, p.535-540

2023

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Phenomenological modeling of critical heat flux: The GRAMP code and its validation

Nuclear engineering and design, 2013-01, Vol.254, p.280-290

2013

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Transient thermal characteristics of submerged vertical heater under seismic excitation

Experimental heat transfer, 2022-11, Vol.35 (7), p.919-937

2022

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Experimental investigation on dominant waves in upward air-water two-phase flow in churn and annular regime

Experimental thermal and fluid science, 2017-02, Vol.81, p.147-163

2017

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Experimental & numerical study of different orifice configurations for helical coil Once Through Steam Generator

Progress in nuclear energy (New series), 2022-01, Vol.143, p.104056, Article 104056

2022

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Phenomenological prediction of CHF under boiling water reactor (BWR) conditions

Progress in nuclear energy (New series), 2011-09, Vol.53 (7), p.874-880

2011

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A new methodology for estimation of initial entrainment fraction in annular flow for improved dryout prediction

Annals of nuclear energy, 2015-01, Vol.75, p.323-330

2015

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Quenching of a Heated Rod: Physical Phenomena, Heat Transfer, and Effect of Nanofluids

Journal of heat transfer, 2016-12, Vol.138 (12)

2016

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Exploring the Use of Alumina Nanofluid as Emergency Coolant for Nuclear Fuel Bundle

Journal of thermal science and engineering applications, 2019-04, Vol.11 (2)

2019

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Investigation on Heat Transfer Behaviour of Inclined Heat Exchanger in a Pool under Earthquake Vibration

Fluid Mechanics and Fluid Power (Vol. 3), 2023, p.529-533

2023

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Investigation on the characteristic of CHF in various flow pattern regimes based on look-up table data

Nuclear engineering and design, 2008, Vol.238 (1), p.170-177

2008

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Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor

Journal of nuclear engineering and radiation science, 2019-10, Vol.5 (4)

2019

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Experimental Demonstration of Safety During Extended Station Blackout in an Integral Test Loop of a Natural Circulation Boiling Water Reactor

Journal of nuclear engineering and radiation science, 2019-10, Vol.5 (4)

2019

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Design and analysis of 19 pin annular fuel rod cluster for pressure tube type boiling water reactor

Nuclear engineering and design, 2014-09, Vol.276, p.64-73

2014

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Design of 33 pin annular fuel rod cluster for Advanced Heavy Water Reactor

Nuclear engineering and design, 2013-03, Vol.256, p.94-101

2013

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Transient heat transfer characteristics of submerged heat source under seismic excitation

International journal of thermal sciences, 2023-02, Vol.184, p.107964, Article 107964

2023

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Experimental assessment of hydrogen removal rate for passive auto catalytic recombiners

Nuclear engineering and design, 2023-06, Vol.407, p.112274, Article 112274

2023

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Analytical model development for investigation on hydrogen management studies in the containment of a nuclear reactor

Nuclear engineering and design, 2024-01, Vol.416, p.112786, Article 112786

2024

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Experimental and analytical investigations on core flow distribution and pressure distribution in the outlet header of a PHWR

Experimental thermal and fluid science, 2002-12, Vol.27 (1), p.11-24

2002

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Thermal Stratification in a Pool With Submerged Heater Under Low Frequency Excitation

Journal of nuclear engineering and radiation science, 2022-07, Vol.8 (3)

2022

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SCADOP: Phenomenological modeling of dryout in nuclear fuel rod bundles

Nuclear engineering and design, 2015-11, Vol.293, p.127-137

2015

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Experimental investigation of effect of spacer on single phase turbulent mixing rate on simulated subchannel of Advanced Heavy Water Reactor

Annals of nuclear energy, 2017-12, Vol.110, p.186-195

2017

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Effect of spacer on the dryout of BWR fuel rod assemblies

Nuclear engineering and design, 2015-12, Vol.294, p.262-273

2015

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Numerical investigation on convective heat transfer in a pool with submerged heat source under seismic condition

Prediction of Vapor Film Thickness Below a Leidenfrost Drop

Numerical Investigation of Single-Phase Convection of Submerged Heat Exchanger under Low Frequency Excitation

Phenomenological modeling of critical heat flux: The GRAMP code and its validation

Transient thermal characteristics of submerged vertical heater under seismic excitation

Experimental investigation on dominant waves in upward air-water two-phase flow in churn and annular regime

Experimental & numerical study of different orifice configurations for helical coil Once Through Steam Generator

Phenomenological prediction of CHF under boiling water reactor (BWR) conditions

A new methodology for estimation of initial entrainment fraction in annular flow for improved dryout prediction

Quenching of a Heated Rod: Physical Phenomena, Heat Transfer, and Effect of Nanofluids

Exploring the Use of Alumina Nanofluid as Emergency Coolant for Nuclear Fuel Bundle

Investigation on Heat Transfer Behaviour of Inclined Heat Exchanger in a Pool under Earthquake Vibration

Investigation on the characteristic of CHF in various flow pattern regimes based on look-up table data

Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor

Experimental Demonstration of Safety During Extended Station Blackout in an Integral Test Loop of a Natural Circulation Boiling Water Reactor

Design and analysis of 19 pin annular fuel rod cluster for pressure tube type boiling water reactor

Design of 33 pin annular fuel rod cluster for Advanced Heavy Water Reactor

Transient heat transfer characteristics of submerged heat source under seismic excitation

Experimental assessment of hydrogen removal rate for passive auto catalytic recombiners

Analytical model development for investigation on hydrogen management studies in the containment of a nuclear reactor

Experimental and analytical investigations on core flow distribution and pressure distribution in the outlet header of a PHWR

Thermal Stratification in a Pool With Submerged Heater Under Low Frequency Excitation

SCADOP: Phenomenological modeling of dryout in nuclear fuel rod bundles

Experimental investigation of effect of spacer on single phase turbulent mixing rate on simulated subchannel of Advanced Heavy Water Reactor

Effect of spacer on the dryout of BWR fuel rod assemblies

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