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Journal Articles

Long-Term Performance of Semimetallic Gaskets

Abdel-Hakim Bouzid, Shubhra Kanti Das

ASME J of Nuclear Rad Sci. July 2023, 9(3): 031801.

Paper No: NERS-22-1036

DOI: https://doi.org/10.1115/1.4056260

Published Online: February 8, 2023

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Topics: Gaskets, Graphite, Leakage, Temperature, Relaxation (Physics), High temperature, Weight (Mass), Stress

Journal Articles

Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One

Davor Grgić, Mario Matijević, Paulina Dučkić, Radomir Ječmenica

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041902.

Paper No: NERS-21-1029

DOI: https://doi.org/10.1115/1.4051447

Published Online: March 16, 2022

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Topics: Accidents, Fuels, Hardware, Neutrons, Nuclear power stations, Particulate matter, Spent nuclear fuels, Storage, Uncertainty, Manufacturing

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

DOI: https://doi.org/10.1115/1.4052974

Published Online: March 15, 2022

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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

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

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031102.

Paper No: NERS-21-1065

DOI: https://doi.org/10.1115/1.4052520

Published Online: March 15, 2022

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Topics: Alloys, Coatings, Corrosion, Hydrogen, Water, Weight (Mass), Zirconium, Absorption, Coating processes, Zirconium alloys

Journal Articles

A Short Inroad to Optimized Compactification of Composite Neutronic Shields

Nassar H. S. Haidar

ASME J of Nuclear Rad Sci. April 2022, 8(2): 024506.

Paper No: NERS-21-1173

DOI: https://doi.org/10.1115/1.4053334

Published Online: February 7, 2022

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Topics: Composite materials, Design, Neutrons, Optimization, Neutron beams, Diffusion (Physics), Weight (Mass)

Journal Articles

Techno-Economic Study on Implementation of Inventory Control Requirements for a Nuclear-Powered Closed-Cycle Gas Turbine Power Plant

Emmanuel O. Osigwe, Arnold Gad-Briggs, Mafel Obhuo, Pericles Pilidis

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031301.

Paper No: NERS-19-1139

DOI: https://doi.org/10.1115/1.4048903

Published Online: February 19, 2021

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Topics: Closed-cycle gas turbines, Compressors, Control systems, Cycles, Fluids, Pressure, Storage tanks, Stress, Temperature, Valves

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

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031102.

Paper No: NERS-19-1053

DOI: https://doi.org/10.1115/1.4045387

Published Online: June 5, 2020

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Topics: Alloys, Coatings, Corrosion, Titanium, Water, Weight (Mass), Zirconium

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

DOI: https://doi.org/10.1115/1.4044530

Published Online: June 5, 2020

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Topics: Alloys, Oxidation, Steam, Steel, Superheating, Weight (Mass), Spallation (Nuclear physics)

Journal Articles

A New Global Variance Reduction Technique Based on Geometry and Energy Splitting/Roulette

Z. Zheng, R. Li, Y. Zhou, Q. Mei, L. Deng

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011102.

Paper No: NERS-18-1130

DOI: https://doi.org/10.1115/1.4045030

Published Online: November 8, 2019

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Topics: Computers, Errors, Fluence (Radiation measurement), Geometry, Neutrons, Particulate matter, Phase space, Photons, Weight (Mass), Dosimeters

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

DOI: https://doi.org/10.1115/1.4042500

Published Online: July 19, 2019

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Topics: Alloys, Coatings, Oxidation, Pressure, Steam, Superheating, Temperature, Water, Weight (Mass), High temperature

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

DOI: https://doi.org/10.1115/1.4043097

Published Online: April 19, 2019

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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

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

DOI: https://doi.org/10.1115/1.4042359

Published Online: April 16, 2019

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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

Nick Tepylo, Xiao Huang, Shengli Jiang, Sami Penttilä

ASME J of Nuclear Rad Sci. January 2019, 5(1): 011014.

Paper No: NERS-18-1016

DOI: https://doi.org/10.1115/1.4040889

Published Online: January 24, 2019

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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

Neutronics Analysis of Small Compact Prismatic Nuclear Reactors for Space Crafts

Xie Yang, Ding She, Lei Shi

ASME J of Nuclear Rad Sci. April 2018, 4(2): 021006.

Paper No: NERS-17-1123

DOI: https://doi.org/10.1115/1.4038774

Published Online: March 5, 2018

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Topics: Accidents, Design, Fuels, Nuclear reactors, Neutrons, Temperature, Uranium, Helium, Graphite, Thermal energy

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

DOI: https://doi.org/10.1115/1.4037668

Published Online: December 4, 2017

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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

DOI: https://doi.org/10.1115/1.4037718

Published Online: December 4, 2017

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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

ASME J of Nuclear Rad Sci. January 2018, 4(1): 011017.

Paper No: NERS-17-1038

DOI: https://doi.org/10.1115/1.4037324

Published Online: December 4, 2017

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

Journal Articles

A Study of the External Exposure Decay Curves as a Function of Several Clinical Parameters for Patients Treated With Therapeutic 131 I

Dimitry Ginzburg, Sophia Lantsberg, Sergio Faermann

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030906.

Paper No: NERS-16-1095

DOI: https://doi.org/10.1115/1.4036433

Published Online: May 25, 2017

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Topics: Biomedicine, Half-life, Radiation (Physics), Weight (Mass), Cancer, Fittings

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

DOI: https://doi.org/10.1115/1.4035549

Published Online: May 25, 2017

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Topics: Alloys, Corrosion, Metals, Oxidation, Supercritical water reactors, Temperature, Weight (Mass), Water, Fuels, Cladding systems (Building)

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

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031007.

Paper No: NERS-15-1097

DOI: https://doi.org/10.1115/1.4032871

Published Online: June 17, 2016

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Topics: Corrosion, Corrosion resistance, Finishes, Flow (Dynamics), Fuels, Oxygen, Stainless steel, Supercritical water reactors, Temperature, Water

Journal citation

NARROW

Long-Term Performance of Semimetallic Gaskets

Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One

Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions

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

A Short Inroad to Optimized Compactification of Composite Neutronic Shields

Techno-Economic Study on Implementation of Inventory Control Requirements for a Nuclear-Powered Closed-Cycle Gas Turbine Power Plant

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

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

A New Global Variance Reduction Technique Based on Geometry and Energy Splitting/Roulette

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

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

Neutronics Analysis of Small Compact Prismatic Nuclear Reactors for Space Crafts

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

A Study of the External Exposure Decay Curves as a Function of Several Clinical Parameters for Patients Treated With Therapeutic 131 I

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

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

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