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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

Effect of Niobium on Sintering Process of Gamma Phase Uranium Alloys Fuel Pellets

Keke Hou, Chao Yan, Peng Wang, Changqing Cao, Jun Lin, Yanguang Cui, Junqiang Lu, Libing Zhu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041101.
Paper No: NERS-22-1130
https://doi.org/10.1115/1.4062795
Published Online: July 17, 2023
View Article titled, Effect of Niobium on Sintering Process of Gamma Phase Uranium Alloys Fuel Pellets
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Topics: Alloys, Fuels, Sintering, Uranium, Thermal conductivity, Density
Journal Articles

Thermophysical Characteristics of Liquid Metal In-Bi-Sn Eutectic (Field's Metal) as a Similarity Coolant

Adam Lipchitz, Glenn Harvel, T. Sunagawa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031301.
Paper No: NERS-21-1079
https://doi.org/10.1115/1.4053632
Published Online: May 26, 2022
View Article titled, Thermophysical Characteristics of Liquid Metal In-Bi-Sn Eutectic (Field's Metal) as a Similarity Coolant
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Topics: Density, Liquid metals, Metals, Temperature, Thermal conductivity, Viscosity, Specific heat, Alloys
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

Effect of Sequential Helium and Nickel Ion Implantation on the Nano-Indentation Hardness of X750 Alloy

Maisaa N. Tawfeeq, Robert J. Klassen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031601.
Paper No: NERS-19-1146
https://doi.org/10.1115/1.4049095
Published Online: March 16, 2021
View Article titled, Effect of Sequential Helium and Nickel Ion Implantation on the Nano-Indentation Hardness of X750 Alloy
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Topics: Alloys, Helium, Ion implantation, Temperature, Nanoindentation, Bubbles, Hardening, Nickel, Heat, Damage
Journal Articles

GTAW Welded Inconel 625 Alloy Fuel Cladding for the Canadian SCWR: Microstructure and Mechanical Property Characterization

Cota-Sanchez German, Xiao Lin
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031304.
Paper No: NERS-20-1053
https://doi.org/10.1115/1.4049278
Published Online: March 16, 2021
View Article titled, GTAW Welded Inconel 625 Alloy Fuel Cladding for the Canadian SCWR: Microstructure and Mechanical Property Characterization
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Topics: Heat, Welding, Cladding systems (Building), Fuels, Alloys, Supercritical water reactors, Mechanical properties, Gas tungsten arc welding, Welded joints
Journal Articles

Microstructural Evaluation of Alloy 800H After SCWL Exposure

D. Marušáková, C. Aparicio, R. Fukač
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2021, 7(2): 024507.
Paper No: NERS-20-1158
https://doi.org/10.1115/1.4049853
Published Online: February 19, 2021
View Article titled, Microstructural Evaluation of Alloy 800H After SCWL Exposure
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Topics: Alloys, X-ray diffraction, Scanning electron microscopy, Water, Electron backscatter diffraction, Raman spectroscopy
Journal Articles

Preparation and Characterization of Nb-1Zr-0.1C Alloy Suitable for Liquid Metal Coolant Channels of High Temperature Reactors

S. Majumdar, J. Kishor, A. N. Behera, B. Vishwanadh, A. Borgohain, R. Kapoor, R. Tewari, V. Kain, Madangopal Krishnan, G. K. Dey, S. Banerjee
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011603.
Paper No: NERS-19-1177
https://doi.org/10.1115/1.4047919
Published Online: October 2, 2020
View Article titled, Preparation and Characterization of Nb-1Zr-0.1C Alloy Suitable for Liquid Metal Coolant Channels of High Temperature Reactors
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Topics: Alloys, Creep, Errors, Cathode ray oscilloscopes, Electron beams, High temperature, Corrosion, Melting
Journal Articles

Ni + and He + Implantation Effects on the Hardness and Microstructure of Heat-Treated X750 Superalloy

Maisaa N. Tawfeeq, Robert J. Klassen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011602.
Paper No: NERS-19-1135
https://doi.org/10.1115/1.4046716
Published Online: October 1, 2020
View Article titled, Ni + and He + Implantation Effects on the Hardness and Microstructure of Heat-Treated X750 Superalloy
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Topics: Alloys, Damage, Electron microscopy, Hardening, Heat, Helium, Ion implantation, Irradiation (Radiation exposure), Superalloys, Testing
Journal Articles

Oxidation Behavior of Alumina-Forming Austenitic Steels in Superheated Steam at 700 °C

Bingjie Xiao, Nick Tepylo, Xiao Huang, Zhangjian Zhou, Sami Penttilä
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031109.
Paper No: NERS-19-1078
https://doi.org/10.1115/1.4044530
Published Online: June 5, 2020
View Article titled, Oxidation Behavior of Alumina-Forming Austenitic Steels in Superheated Steam at 700 °C
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Topics: Alloys, Oxidation, Steam, Steel, Superheating, Weight (Mass), Spallation (Nuclear physics)
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

Effect of Steam Temperature and Pressure on the Oxidation of Potential Coating Alloy FeCrAl for Supercritical Water-Cooled Reactor Application

Bingjie Xiao, Xiao Huang, Qi Yang, Prakash Patnaik
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041204.
Paper No: NERS-18-1081
https://doi.org/10.1115/1.4042500
Published Online: July 19, 2019
View Article titled, Effect of Steam Temperature and Pressure on the Oxidation of Potential Coating Alloy FeCrAl for Supercritical Water-Cooled Reactor Application
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Topics: Alloys, Coatings, Oxidation, Pressure, Steam, Superheating, Temperature, Water, Weight (Mass), High temperature
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

Preliminary Experiments While Designing a Cold Crucible for Metal Melting

David Rot, Jakub Jiřinec
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030911.
Paper No: NERS-18-1121
https://doi.org/10.1115/1.4043199
Published Online: April 16, 2019
View Article titled, Preliminary Experiments While Designing a Cold Crucible for Metal Melting
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Topics: Alloys, Computer simulation, Design, Electromagnetic induction, Inductors, Melting, Metals, Stress, Magnetohydrodynamics, Generators
Journal Articles

Performance of Aluminide and Cr-Modified Aluminide Pack Cementation-Coated Stainless Steel 304 in Supercritical Water at 700 °C

Nick Tepylo, Xiao Huang, Shengli Jiang, Sami Penttilä
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2019, 5(1): 011014.
Paper No: NERS-18-1016
https://doi.org/10.1115/1.4040889
Published Online: January 24, 2019
View Article titled, Performance of Aluminide and Cr-Modified Aluminide Pack Cementation-Coated Stainless Steel 304 in Supercritical Water at 700 °C
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Topics: Coating processes, Coatings, Oxidation, Spallation (Nuclear physics), Stainless steel, Supercritical water reactors, Water, Weight (Mass), X-ray diffraction, Alloys
Journal Articles

Irradiation Issues and Material Selection for Canadian SCWR Components

L. Walters, M. Wright, D. Guzonas
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031005.
Paper No: NERS-17-1045
https://doi.org/10.1115/1.4038367
Published Online: May 16, 2018
View Article titled, Irradiation Issues and Material Selection for Canadian SCWR Components
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Topics: Alloys, Irradiation (Radiation exposure), Supercritical water reactors, Temperature, Neutrons, Fuels, Water, Stainless steel, Helium
Journal Articles

Characteristics of Thermal–Hydraulic and Heat Transfer in Liquid Windowless Target of Accelerator Driven Subcritical

Feng Wang, Qiang Wen, Xue Qin
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031021.
Paper No: NERS-17-1098
https://doi.org/10.1115/1.4039034
Published Online: May 16, 2018
View Article titled, Characteristics of Thermal–Hydraulic and Heat Transfer in Liquid Windowless Target of Accelerator Driven Subcritical
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Topics: Alloys, Flow (Dynamics), Fluids, Heat transfer, Pressure, Cavitation, Computational fluid dynamics, Spallation (Nuclear physics), Coolants, Vapors
Journal Articles

Characterization of Alloy 214 After Exposure to Superheated Steam at 800 °C

Nick Tepylo, Rainier Garcia Sanchez, Xiao Huang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011019.
Paper No: NERS-17-1022
https://doi.org/10.1115/1.4037718
Published Online: December 4, 2017
View Article titled, Characterization of Alloy 214 After Exposure to Superheated Steam at 800 °C
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Topics: Alloys, Steam, Superheating, Weight (Mass), Oxidation, Temperature
Journal Articles

Corrosion Behaviour of Bare and NiCrAlY Coated Alloy 214 in Supercritical Water at 700 °C

Suzan Bsat, Xiao Huang, Sami Penttila
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011017.
Paper No: NERS-17-1038
https://doi.org/10.1115/1.4037324
Published Online: December 4, 2017
View Article titled, Corrosion Behaviour of Bare and NiCrAlY Coated Alloy 214 in Supercritical Water at 700 °C
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Topics: Alloys, Corrosion, Water, Temperature, Oxidation, Weight (Mass), Supercritical water reactors