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Arun K. Nayak

Bhabha Atomic Research Centre
Homi Bhabha National Institute

21

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24

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Experimental investigations on melt coolability with simulated decay heat—The influence of delay time in flooding

2021
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Transition metal compounds as solar selective material

2021 Reviews in Chemical Engineering
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Retention of Molten Corium in Calandria Vessel of Phwr with Moderator Drain Pipe

2020 Journal of Nuclear Engineering and Radiation Science
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Study On Melt Coolability and Water Ingression Through Melt Pool in Scaled Down Core Catcher ߝ the Influence of Vessel Angle

2020 Journal of Nuclear Engineering and Radiation Science
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Sonneting critical heat flux: New insights in boiling multiphase flow

2020 Physics of Fluids
- Sai Raja Gopal Vadlamudi
- Arun K. Nayak
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Investigations on Effect of Lift and Wall Lubrication Forces on the Subcooled Flow Boiling

2020 Journal of Nuclear Engineering and Radiation Science
- Sai Raja Gopal Vadlamudi
- Arun K. Nayak
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Critical Heat Flux On Curved Calandria Vessel of Indian Phwrs During Severe Accident Condition

2020 Journal of Heat Transfer-transactions of The Asme
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Development of correlation for natural convection heat transfer for large horizontal calandria vessel for in-calandria retention of corium in PHWRs

2020 Nuclear Engineering and Design
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Experimental and numerical study to optimize a design of passive moderator cooling system of an advanced nuclear reactor

2019 Nuclear Engineering and Design
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CFD simulation of Departure from Nucleate Boiling in vertical tubes under high pressure and high flow conditions

2019 Nuclear Engineering and Design
- Sai Raja Gopal Vadlamudi
- Arun K. Nayak
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Citations (7)