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P. K. Verma
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Journal Articles

Critical Heat Flux on Curved Calandria Vessel of Indian PHWRs During Severe Accident Condition

P. K. Verma, P. P. Kulkarni, P. Pandey, S. V. Prasad, A. K. Nayak
Journal: Journal of Heat Transfer
Article Type: Research-Article
J. Heat Transfer. February 2021, 143(2): 022101.
Paper No: HT-20-1228
DOI: https://doi.org/10.1115/1.4048823
Published Online: November 16, 2020
View Article titled, Critical Heat Flux on Curved Calandria Vessel of Indian PHWRs During Severe Accident Condition
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Topics: Critical heat flux, Vessels, Accidents, Heavy water reactors, Heat flux, Heat transfer coefficients
Journal Articles

In-Vessel Retention of PHWRs: Experiments at Prototypic Temperatures

Sumit V. Prasad, P. P. Kulkarni, D. C. Yadav, P. K. Verma, A. K. Nayak
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011601.
Paper No: NERS-18-1099
DOI: https://doi.org/10.1115/1.4043999
Published Online: November 29, 2019
View Article titled, In-Vessel Retention of PHWRs: Experiments at Prototypic Temperatures
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Topics: Temperature, Vessels, Heat transfer, Heavy water reactors
Journal Articles

Experimental Demonstration of Safety of AHWR during Stagnation Channel Break Condition in an Integral Test Loop

Mukesh Kumar, A. K. Nayak, Sumit V. Prasad, P. K. Verma, R. K. Singh, Vikas Jain, D. K. Chandraker
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 021005.
Paper No: NERS-17-1053
DOI: https://doi.org/10.1115/1.4038899
Published Online: March 5, 2018
View Article titled, Experimental Demonstration of Safety of AHWR during Stagnation Channel Break Condition in an Integral Test Loop
Click here to open pdf in another window PDF for Experimental Demonstration of Safety of AHWR during Stagnation Channel Break Condition in an Integral Test Loop
Topics: Accidents, Acoustics, Coolants, Design, Flow (Dynamics), Fuels, Heat, Heavy water reactors, Pipes, Pressure
Journal Articles

Experimental Demonstration of AHWR Safety During Prolonged Station Black Out

Mukesh Kumar, P. K. Verma, A. K. Nayak, A. Rama Rao
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041012.
Paper No: NERS-17-1007
DOI: https://doi.org/10.1115/1.4037031
Published Online: July 31, 2017
View Article titled, Experimental Demonstration of AHWR Safety During Prolonged Station Black Out
Click here to open pdf in another window PDF for Experimental Demonstration of AHWR Safety During Prolonged Station Black Out
Topics: Cooling systems, Design, Heat, Safety, Test facilities, Vessels, Water, Temperature, Fukushima nuclear disaster, Japan, 2011