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Journal Articles

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

Javier Ortiz-Villafuerte, Heriberto Sanchez-Mora, Cesar Queral, Melisa Reyes-Fuentes, Edmundo del-Valle-Gallegos

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1021

https://doi.org/10.1115/1.4055011

Published Online: July 15, 2022

View Article titled, Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a BWR STSBO Using MAAP5 and AZTUSIA

Topics: Boiling water reactors, Hydrogen, Uncertainty analysis, Accidents, Simulation, Explosions, Cladding systems (Building), Failure, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations

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

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

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

Petra Gávelová, Patricie Halodová, Daniela Marušáková, Ondřej Libera, Jakub Krejčí, Věra Vrtílková

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

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

Bingjie Xiao, Nick Tepylo, Xiao Huang, Zhangjian Zhou, Sami Penttilä

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

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

Vojtěch Galek, Jaroslav Stoklasa, Jan Hadrava, Roman Vokatý

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

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

Bingjie Xiao, Xiao Huang, Qi Yang, Prakash Patnaik

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

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

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

Topics: Alloys, High temperature, Oxidation, Testing, Transparency, Zirconium, Creep, Microscopy, Electron backscatter diffraction, Cladding systems (Building)

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

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

Topics: Corrosion, Oxygen, Steel, Oxidation, Metals

Journal Articles

Corrosion Experiments on Ceramic Samples Within Molten Salts

Jan Hadrava, Vojtěch Galek, Jaroslav Stoklasa, Jan Hrbek, Kateřina Kunešová, Petr Bezdička, Ivona Sedlářová

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 Article titled, Corrosion Experiments on Ceramic Samples Within Molten Salts

Topics: Ceramics, Corrosion, Oxidation, Porosity, Weight (Mass), X-ray diffraction, Temperature

Journal Articles

The Behavior of Corundum Ceramic in Molten Salt

Vojtěch Galek, Jaroslav Stoklasa, Jan Hadrava, Jan Hrbek, Petr Bezdička, Ivona Sedlářová

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 Article titled, The Behavior of Corundum Ceramic in Molten Salt

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

Nick Tepylo, Xiao Huang, Shengli Jiang, Sami Penttilä

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

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

Carsten Schroer, Valentyn Tsisar, Adeline Durand, Olaf Wedemeyer, Aleksandr Skrypnik, Jürgen Konys

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

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

Jun Wang, Mckinleigh Mccabe, Troy Christopher Haskin, Yingwei Wu, Guanghui Su, Michael L. Corradini

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

Topics: Cladding systems (Building), Oxidation, Sensitivity analysis, Boilers, Simulation, Feedwater, Water, Temperature, Underground injection, Nuclear power stations

Journal Articles

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

Alberto Sáez-Maderuelo, Michael McTaggart, Xiao Huang, César Maffiotte

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

Topics: Alloys, Coatings, Corrosion, Grain boundaries, Oxidation, Steam, Superheating, Temperature, Weight (Mass), Supercritical water reactors

Journal Articles

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

Nick Tepylo, Rainier Garcia Sanchez, Xiao Huang

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

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

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

Topics: Alloys, Corrosion, Water, Temperature, Oxidation, Weight (Mass), Supercritical water reactors

Journal Articles

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

G. Steeves, W. Cook

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

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

Andrea Alfonsi, George L. Mesina, Angelo Zoino, Nolan Anderson, Cristian Rabiti

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

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

Alberto Sáez-Maderuelo, Dolores Gómez-Briceño, César Maffiotte

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

Topics: Pressure, Temperature, Water, Stainless steel, Oxidation, Stress corrosion cracking

Journal Articles

Performance of High-Temperature Materials for Efficient Power Plants: The Waterside Challenge

Pertti Auerkari, Sanni Yli-Olli, Sami Penttilä, Satu Tuurna, Rami Pohja

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031009.

Paper No: NERS-15-1108

https://doi.org/10.1115/1.4032783

Published Online: June 17, 2016

View Article titled, Performance of High-Temperature Materials for Efficient Power Plants: The Waterside Challenge

Topics: High temperature, Oxidation, Steel, Temperature, Corrosion, Thermal power stations, Power stations, Stress, Modeling

Journal citation

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Manuscript

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

Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions

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

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

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

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

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

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

Corrosion Experiments on Ceramic Samples Within Molten Salts

The Behavior of Corundum Ceramic in Molten Salt

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

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

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

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

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

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

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

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

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

Performance of High-Temperature Materials for Efficient Power Plants: The Waterside Challenge

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