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Journal Articles

Investigation of Metal–H 2 O Systems at Elevated Temperatures: Part III: Solubility Data and New Zr Pourbaix Diagrams at 298.15 K and 373.15 K

Graeme J. Francolini, 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): 021603.
Paper No: NERS-23-1112
https://doi.org/10.1115/1.4066341
Published Online: October 3, 2024
View Article titled, Investigation of Metal–H 2 O Systems at Elevated Temperatures: Part III: Solubility Data and New Zr Pourbaix Diagrams at 298.15 K and 373.15 K
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Topics: Temperature, Zirconium, Water
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

Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications

Accepted Manuscript
Armando Nava Dominguez, Xianmin Huang, Songyu Liu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1028
https://doi.org/10.1115/1.4066523
Published Online: September 13, 2024
View Article titled, Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications
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Topics: Computers, Fuels, Manufacturing, Nuclear fuels, Nuclear industry, Supercritical fluids, Water
Journal Articles

Revenue Requirements Method for Assessing the Cost Impact of Fuel Cladding Corrosion in a Supercritical Water-Cooled Small Modular Reactor: A Methodological Review on Life Cycle Costing Corrosion

Alberto D'Ansi Mendoza España
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Review Articles
ASME J of Nuclear Rad Sci. October 2024, 10(4): 040801.
Paper No: NERS-23-1077
https://doi.org/10.1115/1.4064639
Published Online: May 10, 2024
View Article titled, Revenue Requirements Method for Assessing the Cost Impact of Fuel Cladding Corrosion in a Supercritical Water-Cooled Small Modular Reactor: A Methodological Review on Life Cycle Costing Corrosion
Open the PDF for Revenue Requirements Method for Assessing the Cost Impact of Fuel Cladding Corrosion in a Supercritical Water-Cooled Small Modular Reactor: A Methodological Review on Life Cycle Costing Corrosion in another window
Topics: Cladding systems (Building), Corrosion, Fuels, Supercritical water reactors, Water
Journal Articles

Influence of Noncondensable Gas–Dust Mixture on Direct Contact Condensation of Steam at Atmospheric Pressure

Luca Berti, Alessio Pesetti, Michele Raucci, Guglielmo Giambartolomei, Donato Aquaro
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 012301.
Paper No: NERS-23-1020
https://doi.org/10.1115/1.4064066
Published Online: November 30, 2023
View Article titled, Influence of Noncondensable Gas–Dust Mixture on Direct Contact Condensation of Steam at Atmospheric Pressure
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Topics: Condensation, Dust, Steam, Water, Temperature
Journal Articles

Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code

Siniša Šadek, Renato Pavlinac, Karlo Ivanjko, Davor Grgić
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 011301.
Paper No: NERS-23-1016
https://doi.org/10.1115/1.4062799
Published Online: October 20, 2023
View Article titled, Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code
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Topics: Cladding systems (Building), Electricity (Physics), Flow (Dynamics), Hydrogen, Oxidation, Steam, Temperature, Uncertainty, Water, Boundary-value problems
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

Study on the Step by Step Process and Performance of Laser Welding for the Spent Fuel Pool Floor

Le Mei, Xiaochun Zhang, Junbao Zhang, Changlei Shao, Jialei Zhu, Ran Huang, Chongzhi Wu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041803.
Paper No: NERS-23-1056
https://doi.org/10.1115/1.4063008
Published Online: September 15, 2023
View Article titled, Study on the Step by Step Process and Performance of Laser Welding for the Spent Fuel Pool Floor
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Topics: Ferrites (Magnetic materials), Laser welding, Spent nuclear fuels, Water, Welding, Maintenance, Corrosion, Steel, High pressure (Physics), Stainless steel
Journal Articles

ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code

Tommaso Del Moro, Pierdomenico Lorusso, Fabio Giannetti, Mariano Tarantino, Marco Caramello, Daniele Mazzi, Marin Constantin
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041108.
Paper No: NERS-22-1165
https://doi.org/10.1115/1.4056973
Published Online: March 13, 2023
View Article titled, ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code
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Topics: Cycles, Heat exchangers, Sensitivity analysis, Water, Fast neutron reactors, Conceptual design, Temperature, Heat, Bathythermographs, Geometry
Journal Articles

Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres

Olugbenga O. Noah, Johan F. Slabber, Josua P. Meyer
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031403.
Paper No: NERS-22-1020
https://doi.org/10.1115/1.4056239
Published Online: February 8, 2023
View Article titled, Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres
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Topics: Fluids, Heat transfer, Particulate matter, Simulation, Temperature, Flow (Dynamics), Design, Fuels, Safety, Natural convection
Journal Articles

Experimental Investigation on Debris Bed Quenching With Additional Non-Condensable Gas Injection

Markus Petroff, Rudi Kulenovic, Jörg Starflinger
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041702.
Paper No: NERS-21-1028
https://doi.org/10.1115/1.4051876
Published Online: September 3, 2022
View Article titled, Experimental Investigation on Debris Bed Quenching With Additional Non-Condensable Gas Injection
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Topics: Floods, Particulate matter, Quenching (Metalworking), Temperature, Test facilities, Water, Flow (Dynamics), Concretes
Journal Articles

Void Fraction Measurement and Prediction of Two-Phase Boiling Flows in a Tubular Test Section

Qingqing Liu, Julio Diaz, Victor Petrov, Adam Burak, Annalisa Manera, Joseph Kelly, Xiaodong Sun
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021403.
Paper No: NERS-21-1164
https://doi.org/10.1115/1.4055002
Published Online: September 2, 2022
View Article titled, Void Fraction Measurement and Prediction of Two-Phase Boiling Flows in a Tubular Test Section
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Topics: Boiling, Densitometers, Flow (Dynamics), Porosity, X-rays, Water, Flow visualization, Two-phase flow, Instrumentation, Wall temperature
Journal Articles

Assessment of Filtered Containment Venting Strategies for Mitigating Severe Accident Consequences at a Generic Single-Unit CANDU

M. D. Shah, A. C. Morreale, L. S. Lebel
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011701.
Paper No: NERS-22-1025
https://doi.org/10.1115/1.4055258
Published Online: September 2, 2022
View Article titled, Assessment of Filtered Containment Venting Strategies for Mitigating Severe Accident Consequences at a Generic Single-Unit CANDU
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Topics: Accidents, Containment, Failure, Pressure, Water
Journal Articles

Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool

Antonio Guglielmelli, Stefano Ederli, Fulvio Mascari, Federico Rocchi, Pietro Maccari
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041602.
Paper No: NERS-21-1018
https://doi.org/10.1115/1.4054514
Published Online: June 24, 2022
View Article titled, Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool
Open the PDF for Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool in another window
Topics: Accidents, Cooling, Emissions, Fukushima nuclear disaster, Japan, 2011, Meteorology, Nuclear power stations, Simulation, Spent nuclear fuels, Wind, Wind velocity
Journal Articles

Possible Implementation of Ex-Core Measurement in TEPLATOR Graphite Reflector

Eva Vilímová, Tomáš Peltan, Jana Jiřičková
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041505.
Paper No: NERS-21-1013
https://doi.org/10.1115/1.4050990
Published Online: June 15, 2022
View Article titled, Possible Implementation of Ex-Core Measurement in TEPLATOR Graphite Reflector
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Topics: Graphite, Neutron flux, Neutrons, Sensors, Spent nuclear fuels, Water, Fuels
Journal Articles

Water Hammers Exploded the Nuclear Power Plants at Fukushima Daiichi

Robert A. Leishear
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Expert View
ASME J of Nuclear Rad Sci. January 2023, 9(1): 014702.
Paper No: NERS-21-1058
https://doi.org/10.1115/1.4054004
Published Online: June 10, 2022
View Article titled, Water Hammers Exploded the Nuclear Power Plants at Fukushima Daiichi
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Topics: Explosions, Hydrogen, Water
Journal Articles

Radon and Exhalation Rate Measurement of Soil Samples in Al-Amiriya Area in Baghdad Governorate Using a Nuclear Track Detector

Basim Khalaf Rejah
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2023, 9(1): 014501.
Paper No: NERS-22-1001
https://doi.org/10.1115/1.4054619
Published Online: June 7, 2022
View Article titled, Radon and Exhalation Rate Measurement of Soil Samples in Al-Amiriya Area in Baghdad Governorate Using a Nuclear Track Detector
Open the PDF for Radon and Exhalation Rate Measurement of Soil Samples in Al-Amiriya Area in Baghdad Governorate Using a Nuclear Track Detector in another window
Topics: Sensors, Soil, Uranium, Nuclear track detectors, Bridges (Structures), Rocks, Radiation (Physics), Water
Journal Articles

Flash-Boiling Characterization During Ingress of Coolant Event for Dust Issue in ITER

Benjamin Blaisot, Emmanuel Porcheron, Olivier Praud, Véronique Roig
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 032301.
Paper No: NERS-21-1149
https://doi.org/10.1115/1.4053828
Published Online: June 1, 2022
View Article titled, Flash-Boiling Characterization During Ingress of Coolant Event for Dust Issue in ITER
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Topics: Boiling, Coolants, Drops, Dust, Ejectors, Flow (Dynamics), Pressure, Sprays, Vacuum, Water
Journal Articles

Steady-State Subchannel Thermalhydraulic Assessment of a Full-Scale Pressurized Water Reactor-Small Modular Reactor Fuel Assembly With Conventional and Advanced Fuels

Ayman M. Bayomy, Blair P. Bromley, Armando Nava Dominguez, Samuel Kelly
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031601.
Paper No: NERS-21-1184
https://doi.org/10.1115/1.4053829
Published Online: June 1, 2022
View Article titled, Steady-State Subchannel Thermalhydraulic Assessment of a Full-Scale Pressurized Water Reactor-Small Modular Reactor Fuel Assembly With Conventional and Advanced Fuels
Open the PDF for Steady-State Subchannel Thermalhydraulic Assessment of a Full-Scale Pressurized Water Reactor-Small Modular Reactor Fuel Assembly With Conventional and Advanced Fuels in another window
Topics: Fuels, Manufacturing, Temperature, Water
Journal Articles

Physics Modeling for Conceptual Designs of Proposed Experiments in the Zero Energy Deuterium-2 Critical Facility for Testing Small Modular Reactor-Type Fuels

D. G. Watts, F. P. Adams, E. Masala, L. Blomeley, B. P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031501.
Paper No: NERS-21-1118
https://doi.org/10.1115/1.4054079
Published Online: May 26, 2022
View Article titled, Physics Modeling for Conceptual Designs of Proposed Experiments in the Zero Energy Deuterium-2 Critical Facility for Testing Small Modular Reactor-Type Fuels
Open the PDF for Physics Modeling for Conceptual Designs of Proposed Experiments in the Zero Energy Deuterium-2 Critical Facility for Testing Small Modular Reactor-Type Fuels in another window
Topics: Fuels, Modeling, Physics, Pressurized water reactors, Water, Neutrons, High temperature