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Journal Articles

The Heat Capacity of PuO 2 at High Temperature: Molecular Dynamics Calculations

Rolando Calabrese
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041603.
Paper No: NERS-21-1027
https://doi.org/10.1115/1.4054941
Published Online: September 1, 2022
View Article titled, The Heat Capacity of PuO 2 at High Temperature: Molecular Dynamics Calculations
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Topics: Heat capacity, High temperature, Oxygen, Temperature, Molecular dynamics, Enthalpy, Modeling
Journal Articles

Comparison of Corrosion Behavior of the Austenitic Stainless Steel 316 L in Static and Flowing Liquid Lead

Lucia Rozumová, Lukáš Košek, Jan Vít, Anna Hojná, Patricie Halodová
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021605.
Paper No: NERS-20-1096
https://doi.org/10.1115/1.4049719
Published Online: February 19, 2021
View Article titled, Comparison of Corrosion Behavior of the Austenitic Stainless Steel 316 L in Static and Flowing Liquid Lead
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Topics: Corrosion, Oxygen, Stainless steel, Steel
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

Testing Oxygen Nuclear Data Libraries in Research Center Rez

Martin Schulc, Michal Košťál, Evžen Novák, Jan Šimon, Luiz Leal
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021501.
Paper No: NERS-20-1017
https://doi.org/10.1115/1.4048763
Published Online: October 30, 2020
View Article titled, Testing Oxygen Nuclear Data Libraries in Research Center Rez
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Topics: Neutrons, Oxygen, Spectra (Spectroscopy), Water, Testing, Fuels, Neutron sources, Leakage
Journal Articles

Flame-Free Combustion of Radioactive and Hazardous Wastes in the Salt Melt

Vojtěch Galek, Jaroslav Stoklasa, Jan Hadrava, Roman Vokatý
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041305.
Paper No: NERS-19-1180
https://doi.org/10.1115/1.4046911
Published Online: June 3, 2020
View Article titled, Flame-Free Combustion of Radioactive and Hazardous Wastes in the Salt Melt
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Topics: Combustion, Flames, Flue gases, Metals, Oxidation, Temperature, Radioisotopes, Hazardous wastes, Oxygen, Heavy metals
Journal Articles

A Study of the Reproducibility and Diversity of the Supply Chain in Manufacturing Hot Isostatically Pressed Type 316L Stainless Steel Components for the Civil Nuclear Sector

William Kyffin, David Gandy, Barry Burdett
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021116.
Paper No: NERS-18-1112
https://doi.org/10.1115/1.4044752
Published Online: January 29, 2020
View Article titled, A Study of the Reproducibility and Diversity of the Supply Chain in Manufacturing Hot Isostatically Pressed Type 316L Stainless Steel Components for the Civil Nuclear Sector
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Topics: ASTM International, Fracture toughness, Hot pressing, Manufacturing, Materials properties, Oxygen, Stainless steel, Supply chains, Temperature, Tensile strength
Journal Articles

Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels

B. Szpunar, J. A. Szpunar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011108.
Paper No: NERS-19-1046
https://doi.org/10.1115/1.4044751
Published Online: November 8, 2019
View Article titled, Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels
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Topics: Accidents, Atoms, Diffusion (Physics), Fuel rods, Fuels, Helium, Nuclear fuels, Oxygen, Temperature, Temperature gradient
Journal Articles

Corrosion Interaction of 9%Cr Ferritic/Martensitic Steels at 450 and 550 °C With Flowing Pb–Bi Eutectic Containing 10 −7 Mass % Dissolved Oxygen

Valentyn Tsisar, Carsten Schroer, Olaf Wedemeyer, Aleksandr Skrypnik, Jürgen Konys
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 031201.
Paper No: NERS-17-1297
https://doi.org/10.1115/1.4041432
Published Online: May 3, 2019
View Article titled, Corrosion Interaction of 9%Cr Ferritic/Martensitic Steels at 450 and 550 °C With Flowing Pb–Bi Eutectic Containing 10 −7 Mass % Dissolved Oxygen
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Topics: Corrosion, Oxygen, Steel, Oxidation, Metals
Journal Articles

Corrosion in Iron and Steel T91 Caused by Flowing Lead–Bismuth Eutectic at 400 °C and 10 −7 Mass% Dissolved Oxygen

Carsten Schroer, Valentyn Tsisar, Adeline Durand, Olaf Wedemeyer, Aleksandr Skrypnik, Jürgen Konys
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2019, 5(1): 011006.
Paper No: NERS-17-1296
https://doi.org/10.1115/1.4040937
Published Online: January 24, 2019
View Article titled, Corrosion in Iron and Steel T91 Caused by Flowing Lead–Bismuth Eutectic at 400 °C and 10 −7 Mass% Dissolved Oxygen
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Topics: Corrosion, Iron, Oxidation, Oxygen, Steel
Journal Articles

Effect of Structural State and Surface Finishing on Corrosion Behavior of 1.4970 Austenitic Steel at 400 and 500 °C in Flowing Pb-Bi Eutectic With Dissolved Oxygen

Valentyn Tsisar, Carsten Schroer, Olaf Wedemeyer, Aleksandr Skrypnik, Jürgen Konys
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041001.
Paper No: NERS-17-1131
https://doi.org/10.1115/1.4040422
Published Online: September 10, 2018
View Article titled, Effect of Structural State and Surface Finishing on Corrosion Behavior of 1.4970 Austenitic Steel at 400 and 500 °C in Flowing Pb-Bi Eutectic With Dissolved Oxygen
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Topics: Corrosion, Oxygen, Steel, Surface finishing, Polishing
Journal Articles

Effect of Lead-Bismuth Eutectic Oxygen Concentration on the Onset of Dissolution Corrosion in 316 L Austenitic Stainless Steel at 450 °C

Oksana Klok, Konstantina Lambrinou, Serguei Gavrilov, Jun Lim, Iris De Graeve
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031019.
Paper No: NERS-17-1269
https://doi.org/10.1115/1.4039598
Published Online: May 16, 2018
View Article titled, Effect of Lead-Bismuth Eutectic Oxygen Concentration on the Onset of Dissolution Corrosion in 316 L Austenitic Stainless Steel at 450 °C
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Topics: Corrosion, Oxygen, Stainless steel, Steel
Journal Articles

Analysis of Inertization Strategies for the Filtered Containment Venting System in Cofrentes Nuclear Power Plant

Kevin Fernández-Cosials, Gonzalo Jiménez, César Serrano, Luisa Ibáñez, Ángel Peinado
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031016.
Paper No: NERS-17-1065
https://doi.org/10.1115/1.4038595
Published Online: May 16, 2018
View Article titled, Analysis of Inertization Strategies for the Filtered Containment Venting System in Cofrentes Nuclear Power Plant
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Topics: Containment, Hydrogen, Nitrogen, Nuclear power stations, Oxygen, Risk, Combustion, Simulation
Journal Articles

A Density Functional Theory Study on the Diffusion of Fission Gas Atoms in Uranium Dioxide

Qiang Zhao, Zheng Zhang, Xiaoping Ouyang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2018, 4(3): 034503.
Paper No: NERS-17-1278
https://doi.org/10.1115/1.4039885
Published Online: May 16, 2018
View Article titled, A Density Functional Theory Study on the Diffusion of Fission Gas Atoms in Uranium Dioxide
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Topics: Atoms, Density functional theory, Diffusion (Physics), Nuclear fission, Uranium, Elasticity, Fuels, Oxygen
Journal Articles

The Effect of Alkali Metal and Alkaline Earth Metal Impurities on the Iodine-Induced Corrosion of CANDU Fuel Sheathing

Graham A. Ferrier, David Kerr, Joseph Metzler, Evan Veryard, Mohsen Farahani, Paul K. Chan, Mark R. Daymond, Emily C. Corcoran
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041004.
Paper No: NERS-16-1030
https://doi.org/10.1115/1.4037115
Published Online: July 31, 2017
View Article titled, The Effect of Alkali Metal and Alkaline Earth Metal Impurities on the Iodine-Induced Corrosion of CANDU Fuel Sheathing
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Topics: Alkali metals, Coatings, Corrosion, Deflection, Fuels, Metal impurities, Metals, Stress, Vapors, Oxygen
Journal Articles

European Project “Supercritical Water Reactor-Fuel Qualification Test”: Summary of General Corrosion Tests

Radek Novotný, Přemysl Janík, Aki Toivonen, Anna Ruiz, Zoltan Szaraz, Lefu Zhang, Jan Siegl, Petr Haušild, Sami Penttilä, Jan Macák
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2016, 2(3): 031007.
Paper No: NERS-15-1097
https://doi.org/10.1115/1.4032871
Published Online: June 17, 2016
View Article titled, European Project “Supercritical Water Reactor-Fuel Qualification Test”: Summary of General Corrosion Tests
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Topics: Corrosion, Corrosion resistance, Finishes, Flow (Dynamics), Fuels, Oxygen, Stainless steel, Supercritical water reactors, Temperature, Water
Journal Articles

Effect of Thermal Pretreatment on the Corrosion of Stainless Steel in Flowing Supercritical Water

Yinan Jiao, Joseph R. Kish, Graham Steeves, William G. Cook, Wenyue Zheng, David A. Guzonas
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011015.
Paper No: NERS-15-1047
https://doi.org/10.1115/1.4031125
Published Online: December 9, 2015
View Article titled, Effect of Thermal Pretreatment on the Corrosion of Stainless Steel in Flowing Supercritical Water
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Topics: Alloys, Corrosion, Corrosion resistance, Grain boundaries, Intermetallic compounds, Oxygen, Stainless steel, Water, Flow (Dynamics), Testing
Journal Articles

Effect of Oxidation Chemistry of Supercritical Water on Stress Corrosion Cracking of Austenitic Steels

Bin Gong, Yanping Huang, E. Jiang, Yongfu Zhao, Weiwei Liu, Zhiru Zhou
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011019.
Paper No: NERS-15-1109
https://doi.org/10.1115/1.4031076
Published Online: December 9, 2015
View Article titled, Effect of Oxidation Chemistry of Supercritical Water on Stress Corrosion Cracking of Austenitic Steels
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Topics: Chemistry, Fracture (Materials), Steel, Stress corrosion cracking, Water, Water chemistry, Oxidation, Temperature, Supercritical water reactors, Oxygen
Journal Articles

Experimental Study of the Characteristics of Heat Transfer in an HLMC Cross-Flow around Tubes

Aleksei Chernysh, Mikhail Iarmonov, Kirill Makhov, Aleksandr Beznosov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2015, 1(4): 041015.
Paper No: NERS-14-1042
https://doi.org/10.1115/1.4030365
Published Online: September 3, 2015
View Article titled, Experimental Study of the Characteristics of Heat Transfer in an HLMC Cross-Flow around Tubes
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Topics: Coolants, Flow (Dynamics), Heat transfer, Temperature, Oxygen, Liquid metals
Journal Articles

Fully Coupled Simulation of Oxygen and Heat Diffusion for ( U , Pu ) O 2 Fuel in Both Fast-Breeder Reactor and Light-Water Reactor

Wenzhong Zhou, Rong Liu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2015, 1(4): 041007.
Paper No: NERS-15-1020
https://doi.org/10.1115/1.4031033
Published Online: September 3, 2015
View Article titled, Fully Coupled Simulation of Oxygen and Heat Diffusion for ( U , Pu ) O 2 Fuel in Both Fast-Breeder Reactor and Light-Water Reactor
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Topics: Fuels, Light water reactors, Oxygen, Simulation, Temperature, Fast neutron reactors, Diffusion (Physics), Heat, Boundary-value problems, Thermal diffusion