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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

Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a Boiling Water Reactor STSBO Using MAAP5 and AZTUSIA

Javier Ortiz-Villafuerte, Heriberto Sánchez-Mora, César Queral, Melisa Reyes-Fuentes, Edmundo del- Valle-Gallegos
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031701.
Paper No: NERS-22-1021
https://doi.org/10.1115/1.4055011
Published Online: April 22, 2024
View Article titled, Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a Boiling Water Reactor STSBO Using MAAP5 and AZTUSIA
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Topics: Boiling water reactors, Hydrogen, Oxidation, Simulation, Uncertainty analysis, Zirconium, Accidents, Sensitivity analysis, Temperature, Uncertainty
Journal Articles

Mechanical Properties of Irradiated U-10 wt. %Mo Alloy Degraded by Porosity Development

Jason L. Schulthess, Katelyn Baird, Philip Petersen, Daniele Salvato, Hakan Ozaltun, William A. Hanson, Nicholas Ullum, Jeffrey Giglio, James I. Cole
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031601.
Paper No: NERS-23-1114
https://doi.org/10.1115/1.4064779
Published Online: April 17, 2024
View Article titled, Mechanical Properties of Irradiated U-10 wt. %Mo Alloy Degraded by Porosity Development
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Topics: Bending strength, Density, Fuels, Mechanical properties, Nuclear fission, Porosity, Stress, Young's modulus, Zirconium, Alloys
Journal Articles

Electrochemical Activity Measurements of UCl 3 in Molten NaCl-MgCl 2 -UCl 3

Jacob Yankey, Marisa Monreal, Matt Jackson, Michael Simpson
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 030906.
Paper No: NERS-23-1066
https://doi.org/10.1115/1.4064598
Published Online: March 8, 2024
View Article titled, Electrochemical Activity Measurements of UCl 3 in Molten NaCl-MgCl 2 -UCl 3
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Topics: Circuits, Electrodes, Molten salt reactors, Temperature, Zirconium, Electrodeposition, Rods, Electrons
Journal Articles

Cold Crucible Facility for Severe Accident Research at Canadian Nuclear Laboratories

R. David, B. Mitchell, J. H. Spencer, N. Lair, S. M. Petoukhov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2024, 10(2): 024501.
Paper No: NERS-23-1049
https://doi.org/10.1115/1.4063673
Published Online: November 1, 2023
View Article titled, Cold Crucible Facility for Severe Accident Research at Canadian Nuclear Laboratories
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Topics: Accidents, Zirconium, Electromagnetic induction
Journal Articles

Estimate of Neutron Fluence Using Isotope Ratio Method for ZR-2.5NB Materials Irradiated in the National Research Universal Reactor

Xiaolin Wang, Youqing Shi, Grant Bickel, DeAbreu Robert
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2023, 9(3): 034501.
Paper No: NERS-22-1039
https://doi.org/10.1115/1.4055931
Published Online: February 8, 2023
View Article titled, Estimate of Neutron Fluence Using Isotope Ratio Method for ZR-2.5NB Materials Irradiated in the National Research Universal Reactor
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Topics: Fluence (Radiation measurement), Irradiation (Radiation exposure), Isotopes, Neutrons, Zirconium
Journal Articles

Joining of Zirconium Alloys to Nickel Bearing Alloys for In-Core Components

Michel Gaudet, Anne McLellan, Adrian Gerlich, Bruce Williams
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031106.
Paper No: NERS-21-1087
https://doi.org/10.1115/1.4054557
Published Online: May 17, 2022
View Article titled, Joining of Zirconium Alloys to Nickel Bearing Alloys for In-Core Components
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Topics: Alloys, Extruding, Friction welding, Zirconium alloys, Stainless steel, Bearings, Zirconium, Friction, Nickel, Supercritical water reactors
Journal Articles

Weight Gain and Hydrogen Absorption in Supercritical Water At 500 °C of Chromium-Coated Zirconium-Based Alloys: Transverse Versus Longitudinal Direction

K. Khumsa-Ang, S. Rousseau, O. Shiman
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031102.
Paper No: NERS-21-1065
https://doi.org/10.1115/1.4052520
Published Online: March 15, 2022
View Article titled, Weight Gain and Hydrogen Absorption in Supercritical Water At 500 °C of Chromium-Coated Zirconium-Based Alloys: Transverse Versus Longitudinal Direction
Open the PDF for Weight Gain and Hydrogen Absorption in Supercritical Water At 500 °C of Chromium-Coated Zirconium-Based Alloys: Transverse Versus Longitudinal Direction in another window
Topics: Alloys, Coatings, Corrosion, Hydrogen, Water, Weight (Mass), Zirconium, Absorption, Coating processes, Zirconium alloys
Journal Articles

Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions

Sami Penttilä, Juha-Matti Autio, Jari Lydman, Aki Toivonen, Seppo Peltonen, Johanna Lukin
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031103.
Paper No: NERS-21-1069
https://doi.org/10.1115/1.4052974
Published Online: March 15, 2022
View Article titled, Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions
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Topics: Cladding systems (Building), Coatings, Fracture (Materials), Fuels, High temperature steam, Pressurized water reactors, Steam, Zirconium, Temperature, Weight (Mass)
Journal Articles

Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water

Zefeng Wang, Jian Deng, Zhifang Qiu, Xiaoyu Wang, Lei Zhong, Mingjun Zhong
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021403.
Paper No: NERS-20-1202
https://doi.org/10.1115/1.4051875
Published Online: October 19, 2021
View Article titled, Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water
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Topics: Film boiling, Heat flux, Heat transfer, Pool boiling, Quenching (Metalworking), Temperature, Transients (Dynamics), Water, Heat conduction, Heat transfer coefficients
Journal Articles

Deuterium Ingress at the Rolled Joints in CANDU Reactors: Where Does It Come From and How Can It Be Reduced?

S. T. Langille, C. E. Coleman, G. A. McRae
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031801.
Paper No: NERS-20-1069
https://doi.org/10.1115/1.4048313
Published Online: April 1, 2021
View Article titled, Deuterium Ingress at the Rolled Joints in CANDU Reactors: Where Does It Come From and How Can It Be Reduced?
Open the PDF for Deuterium Ingress at the Rolled Joints in CANDU Reactors: Where Does It Come From and How Can It Be Reduced? in another window
Topics: Hydrogen, Pressure, Yttrium, Zirconium, Stainless steel, Fittings
Journal Articles

Microstructure and Nanoindentation Studies of Hydridated Zircaloy-4 Claddings After High Temperature Oxidation

Petra Gávelová, Patricie Halodová, Daniela Marušáková, Ondřej Libera, Jakub Krejčí, Věra Vrtílková
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021604.
Paper No: NERS-20-1110
https://doi.org/10.1115/1.4049053
Published Online: December 14, 2020
View Article titled, Microstructure and Nanoindentation Studies of Hydridated Zircaloy-4 Claddings After High Temperature Oxidation
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Topics: Cladding systems (Building), High temperature, Hydrogen, Nanoindentation, Oxidation, Oxygen, Temperature, Zirconium, Accidents
Journal Articles

On Debris-Fretting Impact—The Study of Oxide and Chromium Layer Application

Marcin Kopeć, Ondřej Pašta, Martina Malá, Patricie Halodová, Ladislav Cvrček, Jakub Krejčí
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021802.
Paper No: NERS-20-1093
https://doi.org/10.1115/1.4048239
Published Online: November 16, 2020
View Article titled, On Debris-Fretting Impact—The Study of Oxide and Chromium Layer Application
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Topics: Cladding systems (Building), Coatings, Fuels, Testing, Wear, Wire, Zirconium, Failure, X-rays, Focused ion beams
Journal Articles

Calculation of Dynamical Phase Diagram in U-Zr Binary System Under Irradiation

Yong Lu, Zheng Jiang, Linyang Li, Cuiping Wang, Yihui Guo, Jiajia Han, Xingjun Liu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011605.
Paper No: NERS-19-1151
https://doi.org/10.1115/1.4047718
Published Online: October 5, 2020
View Article titled, Calculation of Dynamical Phase Diagram in U-Zr Binary System Under Irradiation
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Topics: Diffusion (Physics), Irradiation (Radiation exposure), Phase diagrams, Zirconium
Journal Articles

General Corrosion of Chromium-Coated Zirconium- and Titanium-Based Alloys in Supercritical Water at 500 °C

K. Khumsa-Ang, M. Edwards, S. Rousseau
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031102.
Paper No: NERS-19-1053
https://doi.org/10.1115/1.4045387
Published Online: June 5, 2020
View Article titled, General Corrosion of Chromium-Coated Zirconium- and Titanium-Based Alloys in Supercritical Water at 500 °C
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Topics: Alloys, Coatings, Corrosion, Titanium, Water, Weight (Mass), Zirconium
Journal Articles

From Micro to Nano: Material Characterization Methods for Testing of Nuclear Core and Structural Materials

Petra Gávelová, Patricie Halodová, Hygreeva Kiran Namburi, Iveta Adéla Prokůpková, Marek Mikloš, Jakub Krejčí
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030917.
Paper No: NERS-18-1017
https://doi.org/10.1115/1.4043462
Published Online: May 3, 2019
View Article titled, From Micro to Nano: Material Characterization Methods for Testing of Nuclear Core and Structural Materials
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Topics: Alloys, High temperature, Oxidation, Testing, Transparency, Zirconium, Creep, Microscopy, Electron backscatter diffraction, Cladding systems (Building)
Journal Articles

Simulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated Cladding

Yangbin Deng, Yingwei Wu, Dalin Zhang, Wenxi Tian, G. H. Su, Suizheng Qiu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2019, 5(1): 011015.
Paper No: NERS-17-1293
https://doi.org/10.1115/1.4041194
Published Online: January 24, 2019
View Article titled, Simulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated Cladding
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Topics: Accidents, Cladding systems (Building), Fuels, Stress, Pressure, Simulation, Coatings, Zirconium
Journal Articles

A Study on Hydrogen Emission of Zirconium Hydride

Fu Xiaogang, Qin Bo, Ma Haoran, Zhang Jinquan, Long Bin
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2019, 5(1): 014501.
Paper No: NERS-17-1245
https://doi.org/10.1115/1.4041274
Published Online: January 24, 2019
View Article titled, A Study on Hydrogen Emission of Zirconium Hydride
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Topics: Emissions, Hydrogen, Zirconium, Cladding systems (Building)
Journal Articles

Mechanical Properties of Cubic (U,Zr)O 2

Toru Kitagaki, Takanori Hoshino, Kimihiko Yano, Nobuo Okamura, Hiroshi Ohara, Tetsuo Fukasawa, Kenji Koizumi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031011.
Paper No: NERS-17-1069
https://doi.org/10.1115/1.4039847
Published Online: May 16, 2018
View Article titled, Mechanical Properties of Cubic (U,Zr)O 2
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Topics: Elastic moduli, Fracture toughness, Mechanical properties, Vickers hardness testing, Zirconium, Fracture (Materials), Fuels, Solid solutions
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)