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Journal Articles

Computational Fluid Dynamics Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor

Tomas Korinek, Radek Skoda, Martin Lovecky, Ondrej Burian
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2024, 10(1): 014501.
Paper No: NERS-23-1015
https://doi.org/10.1115/1.4063007
Published Online: October 20, 2023
View Article titled, Computational Fluid Dynamics Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor
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Topics: Computational fluid dynamics, Cooling systems, Flow (Dynamics), Fluid dynamics, Heat, Heavy water reactors, Inertia (Mechanics), Pressure, Temperature, Vessels
Journal Articles

Physics Assessment of the Impact of Modified End Pellets on Axial Power Peaking for Advanced/Nonconventional Uranium-Based Fuels in Pressure Tube Heavy Water Reactors

Huiping V. Yan, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011503.
Paper No: NERS-21-1179
https://doi.org/10.1115/1.4054841
Published Online: September 1, 2022
View Article titled, Physics Assessment of the Impact of Modified End Pellets on Axial Power Peaking for Advanced/Nonconventional Uranium-Based Fuels in Pressure Tube Heavy Water Reactors
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Topics: Fuels, Heavy water reactors, Uranium
Journal Articles

Preliminary Evaluation of the LASSO Method for Prediction of the Relative Power Density Distribution in Mixed Oxide (Pu, DU)O 2 Fuel Pellets

C. V. Anghel, B. P. Bromley, A. A. Prudil, M. J. Welland
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021502.
Paper No: NERS-20-1192
https://doi.org/10.1115/1.4050767
Published Online: October 19, 2021
View Article titled, Preliminary Evaluation of the LASSO Method for Prediction of the Relative Power Density Distribution in Mixed Oxide (Pu, DU)O 2 Fuel Pellets
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Topics: Fuels, Machine learning, Physics, Power density, Neutrons, Heavy water reactors
Includes: Supplementary data
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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
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
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Topics: Pipes, Temperature, Vessels, Heavy water reactors
Journal Articles

Current Status of Reactors Deployment and Small Modular Reactors Development in the World

I. Pioro, R. B. Duffey, P. L. Kirillov, N. Dort-Goltz
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technology Review
ASME J of Nuclear Rad Sci. October 2020, 6(4): 044001.
Paper No: NERS-20-1112
https://doi.org/10.1115/1.4047927
Published Online: September 3, 2020
View Article titled, Current Status of Reactors Deployment and Small Modular Reactors Development in the World
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Topics: Boiling water reactors, China, Construction, Design, Fuels, Licensing, Nuclear power, Nuclear power stations, Nuclear reactors, Pressurized 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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
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
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
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
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Topics: Temperature, Vessels, Heat transfer, Heavy water reactors
Journal Articles

A Study of Superhomogenization Applied to PHWR Lattices

Thomas A. Ferguson, Eleodor M. Nichita
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011109.
Paper No: NERS-19-1049
https://doi.org/10.1115/1.4044748
Published Online: November 8, 2019
View Article titled, A Study of Superhomogenization Applied to PHWR Lattices
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Topics: Fuels, Heavy water reactors, Light water reactors, Water, Diffusion (Physics), Cross section (Physics)
Journal Articles

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

Pradeep Pandey, Parimal P. Kulkarni, Arun Nayak, Sumit V. Prasad
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
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
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Topics: Accidents, Heat, Heavy water reactors, Temperature, Vessels, Water, Design, Boiling, Nuclear power stations, Failure
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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
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
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
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
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Topics: Accidents, Acoustics, Coolants, Design, Flow (Dynamics), Fuels, Heat, Heavy water reactors, Pipes, Pressure
Journal Articles

Special Section: Pressurized Heavy Water Reactors Safety

S. Banerjee, A. K. Nayak, T. (Nithy) Nitheanandan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Guest Editorial
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020301.
Paper No: NERS-17-1005
https://doi.org/10.1115/1.4035852
Published Online: March 1, 2017
View Article titled, Special Section: Pressurized Heavy Water Reactors Safety
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Topics: Design, Heavy water reactors, Safety, Accidents, Water, Nuclear engineering, Thermal hydraulics
Journal Articles

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

Sumit V. Prasad, A. K. Nayak
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
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
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Topics: Accidents, Heat, Heat transfer, Heavy water reactors, Vessels, Water, Temperature, Cooling
Journal Articles

Pressurized Heavy Water Reactor Technology: Its Relevance Today

A. K. Nayak, S. Banerjee
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020901.
Paper No: NERS-17-1006
https://doi.org/10.1115/1.4035856
Published Online: March 1, 2017
View Article titled, Pressurized Heavy Water Reactor Technology: Its Relevance Today
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Topics: Heavy water reactors, Fuels, Uranium
Journal Articles

Thermomechanical Behavior of Coolant Channel Assembly in Heavy Water Reactor Under Severe Plant Condition

A. K. Dureja, P. Seshu, D. N. Pawaskar, R. K. Sinha
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020905.
Paper No: NERS-16-1093
https://doi.org/10.1115/1.4035784
Published Online: March 1, 2017
View Article titled, Thermomechanical Behavior of Coolant Channel Assembly in Heavy Water Reactor Under Severe Plant Condition
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Topics: Contact resistance, Coolants, Deformation, Heat, Heavy water reactors, Manufacturing, Pressure, Temperature, Thermomechanics, Flow (Dynamics)
Journal Articles

Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India

S. Banerjee, H. P. Gupta
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020902.
Paper No: NERS-16-1072
https://doi.org/10.1115/1.4035435
Published Online: March 1, 2017
View Article titled, Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India
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Topics: Heavy water reactors, Safety, Fuels, Design
Journal Articles

Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications

Thambiayah Nitheanandan, X. Cao, J.-H. Choi, D. Dupleac, D.-H. Kim, H. G. Lele, A. K. Nayak, H. P. Rammohan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020903.
Paper No: NERS-16-1084
https://doi.org/10.1115/1.4035726
Published Online: March 1, 2017
View Article titled, Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications
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Topics: Accidents, Heat, Vessels, Water, Heavy water reactors, Computers, Pressure, Fuels, Containment, Boilers
Journal Articles

Current Severe Accident Research and Development Topics for Wolsong PHWR Safety in Korea

Y. M. Song, D. H. Kim, S. Y. Park, J. H. Song
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2017, 3(2): 024501.
Paper No: NERS-16-1063
https://doi.org/10.1115/1.4035690
Published Online: March 1, 2017
View Article titled, Current Severe Accident Research and Development Topics for Wolsong PHWR Safety in Korea
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Topics: Accidents, Containment, Heavy water reactors, Overpressure protection, Safety, Heat, Design, Computers
Journal Articles

Comparison of the Reactivity Effects Calculated by DRAGON and Serpent for a PHWR 37-Element Fuel Bundle

Jawad Haroon, Leslie Kicka, Subhramanyu Mohapatra, Eleodor Nichita, Peter Schwanke
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011011.
Paper No: NERS-16-1008
https://doi.org/10.1115/1.4034571
Published Online: December 20, 2016
View Article titled, Comparison of the Reactivity Effects Calculated by DRAGON and Serpent for a PHWR 37-Element Fuel Bundle
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Topics: Coolants, Density, Fuels, Heavy water reactors, Temperature