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Journal Articles

Retention of Molten Corium in Calandria Vessel of PHWR With Moderator Drain Pipe

Pradeep Pandey, Parimal P. Kulkarni, Arun Nayak, Sumit V. Prasad

Publisher: ASME

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011702.

Paper No: NERS-19-1131

https://doi.org/10.1115/1.4046257

Published Online: October 1, 2020

View Article titled, Retention of Molten Corium in Calandria Vessel of PHWR With Moderator Drain Pipe

Topics: Pipes, Temperature, Vessels, Heavy water reactors

Journal Articles

Experimental Evaluation of Critical Heat Flux in Downward-Facing Boiling on SS304 L Flat Plate Relevant to In-Calandria Retention in PHWRs

Sumit V. Prasad, A. K. Nayak

Publisher: ASME

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031301.

Paper No: NERS-19-1043

https://doi.org/10.1115/1.4044410

Published Online: March 9, 2020

View Article titled, Experimental Evaluation of Critical Heat Flux in Downward-Facing Boiling on SS304 L Flat Plate Relevant to In-Calandria Retention in PHWRs

Topics: Boiling, Critical heat flux, Flat plates, Heavy water reactors, Water, Heat, Subcooling

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

Publisher: ASME

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011601.

Paper No: NERS-18-1099

https://doi.org/10.1115/1.4043999

Published Online: November 29, 2019

View Article titled, In-Vessel Retention of PHWRs: Experiments at Prototypic Temperatures

Topics: Temperature, Vessels, Heat transfer, Heavy water reactors

Journal Articles

Evaluation of Dump Tank Coolability in PHWRs During Late-Phase Severe Accident

Pradeep Pandey, Parimal P. Kulkarni, Arun Nayak, Sumit V. Prasad

Publisher: ASME

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041601.

Paper No: NERS-18-1080

https://doi.org/10.1115/1.4043108

Published Online: July 19, 2019

View Article titled, Evaluation of Dump Tank Coolability in PHWRs During Late-Phase Severe Accident

Topics: Accidents, Heat, Heavy water reactors, Temperature, Vessels, Water, Design, Boiling, Nuclear power stations, Failure

Journal Articles

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

A. K. Nayak, Mukesh Kumar, Sumit V. Prasad, V. Jain, D. K. Chandraker

Publisher: ASME

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041203.

Paper No: NERS-18-1079

https://doi.org/10.1115/1.4042852

Published Online: July 19, 2019

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

Topics: Heat, Test facilities, Water, Cavities, Earthquakes, Heat sinks, Boiling water reactors, Flow (Dynamics), Fukushima nuclear disaster, Japan, 2011, Fracture (Materials)

Journal Articles

Experimental Study on Melt Coolability Capability of Calandria Vault Water During Severe Accident in Indian PHWRs for Prolonged Duration

Sumit V. Prasad, A. K. Nayak

Publisher: ASME

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031014.

Paper No: NERS-17-1062

https://doi.org/10.1115/1.4039636

Published Online: May 16, 2018

View Article titled, Experimental Study on Melt Coolability Capability of Calandria Vault Water During Severe Accident in Indian PHWRs for Prolonged Duration

Topics: Accidents, Boiling, Heat transfer, Heat transfer coefficients, Heavy water reactors, Temperature, Vessels, Water, Heat, Natural convection

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

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2018, 4(2): 021005.

Paper No: NERS-17-1053

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

Topics: Accidents, Acoustics, Coolants, Design, Flow (Dynamics), Fuels, Heat, Heavy water reactors, Pipes, Pressure

Journal Articles

In-Calandria Retention of Corium in PHWR: Experimental Investigation and Remaining Issues

Sumit V. Prasad, A. K. Nayak

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2017, 3(2): 020909.

Paper No: NERS-16-1066

https://doi.org/10.1115/1.4035691

Published Online: March 1, 2017

View Article titled, In-Calandria Retention of Corium in PHWR: Experimental Investigation and Remaining Issues

Topics: Accidents, Heat, Heat transfer, Heavy water reactors, Vessels, Water, Temperature, Cooling

Journal citation

NARROW

Retention of Molten Corium in Calandria Vessel of PHWR With Moderator Drain Pipe

Experimental Evaluation of Critical Heat Flux in Downward-Facing Boiling on SS304 L Flat Plate Relevant to In-Calandria Retention in PHWRs

In-Vessel Retention of PHWRs: Experiments at Prototypic Temperatures

Evaluation of Dump Tank Coolability in PHWRs During Late-Phase Severe Accident

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

Experimental Study on Melt Coolability Capability of Calandria Vault Water During Severe Accident in Indian PHWRs for Prolonged Duration

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

In-Calandria Retention of Corium in PHWR: Experimental Investigation and Remaining Issues

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