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Journal Articles

Investigation of Metal–H 2 O Systems at Elevated Temperatures: Part I. Development of a Solubility Apparatus Specialized for Super-Ambient Conditions

Olga Y. Palazhchenko, Matthew H. Kaye
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021601.
Paper No: NERS-23-1110
https://doi.org/10.1115/1.4066339
Published Online: September 30, 2024
View Article titled, Investigation of Metal–H 2 O Systems at Elevated Temperatures: Part I. Development of a Solubility Apparatus Specialized for Super-Ambient Conditions
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Topics: Equilibrium (Physics), Metals, Temperature, Vessels, Water, Instrumentation
Journal Articles

Heat Flux Correlations for Condensation from Steam and Air Mixtures on Vertical Flat Plates

Accepted Manuscript
Michio Murase, Toshiya Takaki
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1021
https://doi.org/10.1115/1.4066343
Published Online: August 26, 2024
View Article titled, Heat Flux Correlations for Condensation from Steam and Air Mixtures on Vertical Flat Plates
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Topics: Condensation, Flat plates, Heat flux, Steam, Computational fluid dynamics, Flow (Dynamics), Natural convection, Accidents, Boundary-value problems, Containment vessels
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

Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention

Ryotaro Sasaki, Akifumi Yamaji, Kyota Uchimura
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021501.
Paper No: NERS-21-1135
https://doi.org/10.1115/1.4053827
Published Online: June 15, 2022
View Article titled, Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention
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Topics: Design, Vessels, Cycles, Fuels, Temperature, Fast neutron reactors, Small modular reactors
Journal Articles

Experimental Investigation of Melt Coolability Behavior in an Ex-Vessel Core Catcher: The Effect of Flooding Time

Ganesh V, Parimal P. Kulkarni, Arun K. Nayak
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031401.
Paper No: NERS-21-1060
https://doi.org/10.1115/1.4053220
Published Online: May 26, 2022
View Article titled, Experimental Investigation of Melt Coolability Behavior in an Ex-Vessel Core Catcher: The Effect of Flooding Time
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Topics: Floods, Temperature, Vessels, Water
Journal Articles

Deposition of ITER Vacuum Vessel Dust Inside the Pressure Suppression System During a Loss of Coolant Accident: Experimental and Numerical Analyses

Miriam Ibba, Alessio Pesetti, Michele Raucci, Flavio Parozzi, Roberta Lazzeri, Donato Aquaro
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 042301.
Paper No: NERS-21-1025
https://doi.org/10.1115/1.4050768
Published Online: March 16, 2022
View Article titled, Deposition of ITER Vacuum Vessel Dust Inside the Pressure Suppression System During a Loss of Coolant Accident: Experimental and Numerical Analyses
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Topics: Dust, Water, Containers, Vessels, Pipes
Journal Articles

Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage

Aleksander Grah, Haileyesus Tsige-Tamirat, Joel Guidez, Antoine Gerschenfeld, Konstantin Mikityuk, Janos Bodi, Enrico Girardi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011314.
Paper No: NERS-20-1204
https://doi.org/10.1115/1.4051292
Published Online: September 20, 2021
View Article titled, Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage
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Topics: Computational fluid dynamics, Concretes, Cooling, Cooling systems, Design, Heat, Heat flux, Leakage, Reactor vessels, Safety
Journal Articles

Modeling of Reactivity Effects and Transient Behavior of Large Sodium Fast Reactor

Alexander Ponomarev, Konstantin Mikityuk
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011313.
Paper No: NERS-20-1186
https://doi.org/10.1115/1.4051514
Published Online: September 13, 2021
View Article titled, Modeling of Reactivity Effects and Transient Behavior of Large Sodium Fast Reactor
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Topics: Flow (Dynamics), Fuels, Modeling, Rods, Sodium, Sodium fast reactors, Temperature, Transients (Dynamics), Electrical conductance, Heat
Journal Articles

New Reactor Safety Measures for the European Sodium Fast Reactor—Part I: Conceptual Design

Joel Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi, Bernard Carluec
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011311.
Paper No: NERS-20-1059
https://doi.org/10.1115/1.4051364
Published Online: August 12, 2021
View Article titled, New Reactor Safety Measures for the European Sodium Fast Reactor—Part I: Conceptual Design
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Topics: Heat, Safety, Sodium, Vessels, Pumps, Design, Natural convection, Roofs, Leakage, Water
Journal Articles

New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment

Joel Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi, Jeremy Bittan, Aleksander Grah, Haileyesus Tsige-Tamirat, Pablo Romojaro, Francisco Álvarez-Velarde, Bernard Carluec
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011312.
Paper No: NERS-20-1080
https://doi.org/10.1115/1.4051723
Published Online: August 12, 2021
View Article titled, New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment
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Topics: Cooling systems, Design, Heat, Heat transfer, Pumps, Safety, Sodium, Sodium fast reactors, Temperature, Vessels
Journal Articles

Preliminary Assessment of Decay Heat Removal Systems in the ESFR-SMART Design: The Role of Natural Air Convection Around Steam Generators Outer Shells in Accidental Conditions

Jeremy Bittan, Clement Bore, Joel Guidez
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2021, 7(4): 041301.
Paper No: NERS-20-1079
https://doi.org/10.1115/1.4048991
Published Online: April 16, 2021
View Article titled, Preliminary Assessment of Decay Heat Removal Systems in the ESFR-SMART Design: The Role of Natural Air Convection Around Steam Generators Outer Shells in Accidental Conditions
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Topics: Boilers, Heat, Reactor vessels, Sodium, Temperature, Vessels, Shells, Design, Energy budget (Physics), Pumps
Journal Articles

Passive and Walk-Away Safe Small and Microreactors for Electricity Generation and Production of Process Heat for Industrial Uses

Mohamed S. El-Genk, Timothy M. Schriener, Luis M. Palomino
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031302.
Paper No: NERS-20-1023
https://doi.org/10.1115/1.4047920
Published Online: February 19, 2021
View Article titled, Passive and Walk-Away Safe Small and Microreactors for Electricity Generation and Production of Process Heat for Industrial Uses
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Topics: Electric power generation, Fuels, Heat, Neutrons, Safety, Sodium, Vessels, Design, Metals, Steel
Journal Articles

A Comparative Study on Severe Accident Phenomena Related to Melt Progression in Sodium Fast Reactors and Pressurized Water Reactors

Andrea Bachrata, Fréderic Bertrand, Nathalie Marie, Fréderic Serre
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Review Articles
ASME J of Nuclear Rad Sci. July 2021, 7(3): 030801.
Paper No: NERS-20-1040
https://doi.org/10.1115/1.4047921
Published Online: November 11, 2020
View Article titled, A Comparative Study on Severe Accident Phenomena Related to Melt Progression in Sodium Fast Reactors and Pressurized Water Reactors
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Topics: Accidents, Pressurized water reactors, Sodium fast reactors, Safety, Vessels
Journal Articles

Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks

Lorenzo Basili, Rosa Lo Frano, Marco Olcese, Igor Sekachev, Donato Aquaro
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 012301.
Paper No: NERS-19-1156
https://doi.org/10.1115/1.4048007
Published Online: October 5, 2020
View Article titled, Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks
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Topics: Accidents, Computational fluid dynamics, Design, Flanges, Insulation, Pressure, Stress, Temperature, Temperature gradient, Thermal analysis
Journal Articles

Study on Melt Coolability and Water Ingression Through Melt Pool in Scaled Down Core Catcher—The Influence of Vessel Angle

Ganesh V., Parimal P. Kulkarni, Arun K. Nayak
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011301.
Paper No: NERS-19-1182
https://doi.org/10.1115/1.4048235
Published Online: October 5, 2020
View Article titled, Study on Melt Coolability and Water Ingression Through Melt Pool in Scaled Down Core Catcher—The Influence of Vessel Angle
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Topics: Temperature, Vessels, Water
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

Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident

Mahesh Kumar Yadav, Maneesh Punetha, Abhinav Bhanawat, Sameer Khandekar, Pavan K. Sharma
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041108.
Paper No: NERS-19-1164
https://doi.org/10.1115/1.4046910
Published Online: September 4, 2020
View Article titled, Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident
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Topics: Accidents, Condensation, Heat flux, Heat transfer, Pressure, Steady state, Steam, Temperature, Transients (Dynamics), Containment
Journal Articles

Criticality Characteristics and Sensitivity Analysis of Fukushima Debris Beds Containing MCCI Products

María Freiría López, Michael Buck, Jörg Starflinger
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041110.
Paper No: NERS-19-1166
https://doi.org/10.1115/1.4047094
Published Online: September 4, 2020
View Article titled, Criticality Characteristics and Sensitivity Analysis of Fukushima Debris Beds Containing MCCI Products
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Topics: Concretes, Water, Fukushima nuclear disaster, Japan, 2011, Vessels, Sensitivity analysis
Journal Articles

Analysis of the Effect of Vessel Failure and Melt Release on Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic Boiling Water Reactor Using ROAAM+ Framework

Sergey Galushin, Dmitry Grishchenko, Pavel Kudinov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041113.
Paper No: NERS-19-1170
https://doi.org/10.1115/1.4047552
Published Online: September 4, 2020
View Article titled, Analysis of the Effect of Vessel Failure and Melt Release on Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic Boiling Water Reactor Using ROAAM+ Framework
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Topics: Boiling water reactors, Containment, Explosions, Failure, Steam, Vessels, Risk, Accidents, Uncertainty
Journal Articles

Postoperation Dose Rate Estimates for the Very-Small, Long-Life, Modular Reactor

Luis M. Palomino, Mohamed S. El-Genk, Timothy M. Schriener
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031302.
Paper No: NERS-19-1045
https://doi.org/10.1115/1.4045297
Published Online: March 9, 2020
View Article titled, Postoperation Dose Rate Estimates for the Very-Small, Long-Life, Modular Reactor
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Topics: Cladding systems (Building), Emissions, Fuels, Neutrons, Photons, Steel, Vessels, Storage, Radioactivity, Isotopes