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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

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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 Articletitled, 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

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

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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 Articletitled, 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

Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions

Open Access
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 Articletitled, 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

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

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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 Articletitled, 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

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

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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 Articletitled, 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

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

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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 Articletitled, 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

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

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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 Articletitled, 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

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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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 Articletitled, Corrosion Interaction of 9%Cr Ferritic/Martensitic Steels at 450 and 550 °C With Flowing Pb–Bi Eutectic Containing 10 −7 Mass % Dissolved Oxygen
Open the PDF for Corrosion Interaction of 9%Cr Ferritic/Martensitic Steels at 450 and 550 °C With Flowing Pb–Bi Eutectic Containing 10 −7 Mass % Dissolved Oxygen in another window
Topics: Corrosion, Oxygen, Steel, Oxidation, Metals
Journal Articles

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

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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 Articletitled, From Micro to Nano: Material Characterization Methods for Testing of Nuclear Core and Structural Materials
Open the PDF for From Micro to Nano: Material Characterization Methods for Testing of Nuclear Core and Structural Materials in another window
Topics: Alloys, High temperature, Oxidation, Testing, Transparency, Zirconium, Creep, Microscopy, Electron backscatter diffraction, Cladding systems (Building)
Journal Articles

Corrosion Experiments on Ceramic Samples Within Molten Salts

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Jan Hadrava, Vojtěch Galek, Jaroslav Stoklasa, Jan Hrbek, Kateřina Kunešová, Petr Bezdička, Ivona Sedlářová
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030910.
Paper No: NERS-18-1059
https://doi.org/10.1115/1.4043097
Published Online: April 19, 2019
View Articletitled, Corrosion Experiments on Ceramic Samples Within Molten Salts
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Topics: Ceramics, Corrosion, Oxidation, Porosity, Weight (Mass), X-ray diffraction, Temperature
Journal Articles

The Behavior of Corundum Ceramic in Molten Salt

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Vojtěch Galek, Jaroslav Stoklasa, Jan Hadrava, Jan Hrbek, Petr Bezdička, Ivona Sedlářová
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030905.
Paper No: NERS-18-1058
https://doi.org/10.1115/1.4042359
Published Online: April 16, 2019
View Articletitled, The Behavior of Corundum Ceramic in Molten Salt
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Topics: Ceramics, Oxidation, Porosity, Weight (Mass), X-ray diffraction, Organic wastes, Water
Journal Articles

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

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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 Articletitled, Performance of Aluminide and Cr-Modified Aluminide Pack Cementation-Coated Stainless Steel 304 in Supercritical Water at 700 °C
Open the PDF for Performance of Aluminide and Cr-Modified Aluminide Pack Cementation-Coated Stainless Steel 304 in Supercritical Water at 700 °C in another window
Topics: Coating processes, Coatings, Oxidation, Spallation (Nuclear physics), Stainless steel, Supercritical water reactors, Water, Weight (Mass), X-ray diffraction, Alloys
Journal Articles

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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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 Articletitled, Corrosion in Iron and Steel T91 Caused by Flowing Lead–Bismuth Eutectic at 400 °C and 10 −7 Mass% Dissolved Oxygen
Open the PDF for Corrosion in Iron and Steel T91 Caused by Flowing Lead–Bismuth Eutectic at 400 °C and 10 −7 Mass% Dissolved Oxygen in another window
Topics: Corrosion, Iron, Oxidation, Oxygen, Steel
Journal Articles

Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant

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Jun Wang, Mckinleigh Mccabe, Troy Christopher Haskin, Yingwei Wu, Guanghui Su, Michael L. Corradini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041002.
Paper No: NERS-17-1163
https://doi.org/10.1115/1.4040887
Published Online: September 10, 2018
View Articletitled, Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant
Open the PDF for Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant in another window
Topics: Cladding systems (Building), Oxidation, Sensitivity analysis, Boilers, Simulation, Feedwater, Water, Temperature, Underground injection, Nuclear power stations
Journal Articles

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

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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 Articletitled, 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

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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 Articletitled, 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
Journal Articles

Microstructure Study of NiCrAlY and FeCrAlY Exposed to Superheated Steam at 800 °C

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Alberto Sáez-Maderuelo, Michael McTaggart, Xiao Huang, César Maffiotte
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011015.
Paper No: NERS-17-1039
https://doi.org/10.1115/1.4037668
Published Online: December 4, 2017
View Articletitled, Microstructure Study of NiCrAlY and FeCrAlY Exposed to Superheated Steam at 800 °C
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Topics: Alloys, Coatings, Corrosion, Grain boundaries, Oxidation, Steam, Superheating, Temperature, Weight (Mass), Supercritical water reactors
Journal Articles

Development of Kinetic Models for the Long-Term Corrosion Behavior of Candidate Alloys for the Canadian SCWR

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G. Steeves, W. Cook
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2017, 3(3): 031001.
Paper No: NERS-15-1101
https://doi.org/10.1115/1.4035549
Published Online: May 25, 2017
View Articletitled, Development of Kinetic Models for the Long-Term Corrosion Behavior of Candidate Alloys for the Canadian SCWR
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Topics: Alloys, Corrosion, Metals, Oxidation, Supercritical water reactors, Temperature, Weight (Mass), Water, Fuels, Cladding systems (Building)
Journal Articles

Combining RAVEN, RELAP5-3D, and PHISICS for Fuel Cycle and Core Design Analysis for New Cladding Criteria

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Andrea Alfonsi, George L. Mesina, Angelo Zoino, Nolan Anderson, Cristian Rabiti
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020906.
Paper No: NERS-16-1120
https://doi.org/10.1115/1.4035851
Published Online: March 1, 2017
View Articletitled, Combining RAVEN, RELAP5-3D, and PHISICS for Fuel Cycle and Core Design Analysis for New Cladding Criteria
Open the PDF for Combining RAVEN, RELAP5-3D, and PHISICS for Fuel Cycle and Core Design Analysis for New Cladding Criteria in another window
Topics: Accidents, Cladding systems (Building), Coolants, Cycles, Design, Flow (Dynamics), Fuels, Nuclear fuel cycle, Oxidation, Safety
Journal Articles

Influence of Changes in Pressure and Temperature of Supercritical Water on the Susceptibility to Stress Corrosion Cracking of 316L Austenitic Stainless Steel

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Alberto Sáez-Maderuelo, Dolores Gómez-Briceño, César Maffiotte
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011009.
Paper No: NERS-15-1100
https://doi.org/10.1115/1.4032780
Published Online: December 20, 2016
View Articletitled, Influence of Changes in Pressure and Temperature of Supercritical Water on the Susceptibility to Stress Corrosion Cracking of 316L Austenitic Stainless Steel
Open the PDF for Influence of Changes in Pressure and Temperature of Supercritical Water on the Susceptibility to Stress Corrosion Cracking of 316L Austenitic Stainless Steel in another window
Topics: Pressure, Temperature, Water, Stainless steel, Oxidation, Stress corrosion cracking