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Journal Articles

Estimate of Neutron Fluence Using Isotope Ratio Method for ZR-2.5NB Materials Irradiated in the National Research Universal Reactor

Xiaolin Wang, Youqing Shi, Grant Bickel, DeAbreu Robert

ASME J of Nuclear Rad Sci. July 2023, 9(3): 034501.

Paper No: NERS-22-1039

https://doi.org/10.1115/1.4055931

Published Online: February 8, 2023

View Article titled, Estimate of Neutron Fluence Using Isotope Ratio Method for ZR-2.5NB Materials Irradiated in the National Research Universal Reactor

Topics: Fluence (Radiation measurement), Irradiation (Radiation exposure), Isotopes, Neutrons, Zirconium

Journal Articles

Joining of Zirconium Alloys to Nickel Bearing Alloys for In-Core Components

Michel Gaudet, Anne McLellan, Adrian Gerlich, Bruce Williams

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

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

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

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

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

Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water

Zefeng Wang, Jian Deng, Zhifang Qiu, Xiaoyu Wang, Lei Zhong, Mingjun Zhong

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021403.

Paper No: NERS-20-1202

https://doi.org/10.1115/1.4051875

Published Online: October 19, 2021

View Article titled, Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water

Topics: Film boiling, Heat flux, Heat transfer, Pool boiling, Quenching (Metalworking), Temperature, Transients (Dynamics), Water, Heat conduction, Heat transfer coefficients

Journal Articles

Deuterium Ingress at the Rolled Joints in CANDU Reactors: Where Does It Come From and How Can It Be Reduced?

S. T. Langille, C. E. Coleman, G. A. McRae

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031801.

Paper No: NERS-20-1069

https://doi.org/10.1115/1.4048313

Published Online: April 1, 2021

View Article titled, Deuterium Ingress at the Rolled Joints in CANDU Reactors: Where Does It Come From and How Can It Be Reduced?

Topics: Hydrogen, Pressure, Yttrium, Zirconium, Stainless steel, Fittings

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

On Debris-Fretting Impact—The Study of Oxide and Chromium Layer Application

Marcin Kopeć, Ondřej Pašta, Martina Malá, Patricie Halodová, Ladislav Cvrček, Jakub Krejčí

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021802.

Paper No: NERS-20-1093

https://doi.org/10.1115/1.4048239

Published Online: November 16, 2020

View Article titled, On Debris-Fretting Impact—The Study of Oxide and Chromium Layer Application

Topics: Cladding systems (Building), Coatings, Fuels, Testing, Wear, Wire, Zirconium, Failure, X-rays, Focused ion beams

Journal Articles

Calculation of Dynamical Phase Diagram in U-Zr Binary System Under Irradiation

Yong Lu, Zheng Jiang, Linyang Li, Cuiping Wang, Yihui Guo, Jiajia Han, Xingjun Liu

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011605.

Paper No: NERS-19-1151

https://doi.org/10.1115/1.4047718

Published Online: October 5, 2020

View Article titled, Calculation of Dynamical Phase Diagram in U-Zr Binary System Under Irradiation

Topics: Diffusion (Physics), Irradiation (Radiation exposure), Phase diagrams, Zirconium

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

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

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

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

Simulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated Cladding

Yangbin Deng, Yingwei Wu, Dalin Zhang, Wenxi Tian, G. H. Su, Suizheng Qiu

ASME J of Nuclear Rad Sci. January 2019, 5(1): 011015.

Paper No: NERS-17-1293

https://doi.org/10.1115/1.4041194

Published Online: January 24, 2019

View Article titled, Simulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated Cladding

Topics: Accidents, Cladding systems (Building), Fuels, Stress, Pressure, Simulation, Coatings, Zirconium

Journal Articles

A Study on Hydrogen Emission of Zirconium Hydride

Fu Xiaogang, Qin Bo, Ma Haoran, Zhang Jinquan, Long Bin

ASME J of Nuclear Rad Sci. January 2019, 5(1): 014501.

Paper No: NERS-17-1245

https://doi.org/10.1115/1.4041274

Published Online: January 24, 2019

View Article titled, A Study on Hydrogen Emission of Zirconium Hydride

Topics: Emissions, Hydrogen, Zirconium, Cladding systems (Building)

Journal Articles

Mechanical Properties of Cubic (U,Zr)O 2

Toru Kitagaki, Takanori Hoshino, Kimihiko Yano, Nobuo Okamura, Hiroshi Ohara, Tetsuo Fukasawa, Kenji Koizumi

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031011.

Paper No: NERS-17-1069

https://doi.org/10.1115/1.4039847

Published Online: May 16, 2018

View Article titled, Mechanical Properties of Cubic (U,Zr)O 2

Topics: Elastic moduli, Fracture toughness, Mechanical properties, Vickers hardness testing, Zirconium, Fracture (Materials), Fuels, Solid solutions

Journal Articles

Analysis of Late Phase Severe Accident Phenomena in CANDU Plant

D. Dupleac

ASME J of Nuclear Rad Sci. April 2017, 3(2): 020904.

Paper No: NERS-16-1085

https://doi.org/10.1115/1.4035416

Published Online: March 1, 2017

View Article titled, Analysis of Late Phase Severe Accident Phenomena in CANDU Plant

Topics: Accidents, Vessels, Water, Zirconium, Steam, Failure, Heat transfer coefficients, Temperature

Journal Articles

Thermomechanical Behavior of Coolant Channel Assembly in Heavy Water Reactor Under Severe Plant Condition

A. K. Dureja, P. Seshu, D. N. Pawaskar, R. K. Sinha

ASME J of Nuclear Rad Sci. April 2017, 3(2): 020905.

Paper No: NERS-16-1093

https://doi.org/10.1115/1.4035784

Published Online: March 1, 2017

View Article titled, Thermomechanical Behavior of Coolant Channel Assembly in Heavy Water Reactor Under Severe Plant Condition

Topics: Contact resistance, Coolants, Deformation, Heat, Heavy water reactors, Manufacturing, Pressure, Temperature, Thermomechanics, Flow (Dynamics)

Journal Articles

Combined Effect of Irradiation, Temperature, and Water Coolant Flow on Corrosion of Zr-, Ni–Cr-, and Fe–Cr-Based Alloys

O. S. Bakai, V. M. Boriskin, A. M. Dovbnya, S. V. Dyuldya, D. A. Guzonas

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021007.

Paper No: NERS-15-1077

https://doi.org/10.1115/1.4031126

Published Online: February 29, 2016

View Article titled, Combined Effect of Irradiation, Temperature, and Water Coolant Flow on Corrosion of Zr-, Ni–Cr-, and Fe–Cr-Based Alloys

Topics: Alloys, Corrosion, Irradiation (Radiation exposure), Temperature, Water, Zirconium, Electrons, Chemistry, Oxidation, Coolants

Journal citation

NARROW

Estimate of Neutron Fluence Using Isotope Ratio Method for ZR-2.5NB Materials Irradiated in the National Research Universal Reactor

Joining of Zirconium Alloys to Nickel Bearing Alloys for In-Core Components

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

Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions

Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water

Deuterium Ingress at the Rolled Joints in CANDU Reactors: Where Does It Come From and How Can It Be Reduced?

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

On Debris-Fretting Impact—The Study of Oxide and Chromium Layer Application

Calculation of Dynamical Phase Diagram in U-Zr Binary System Under Irradiation

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

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

Simulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated Cladding

A Study on Hydrogen Emission of Zirconium Hydride

Mechanical Properties of Cubic (U,Zr)O 2

Analysis of Late Phase Severe Accident Phenomena in CANDU Plant

Thermomechanical Behavior of Coolant Channel Assembly in Heavy Water Reactor Under Severe Plant Condition

Combined Effect of Irradiation, Temperature, and Water Coolant Flow on Corrosion of Zr-, Ni–Cr-, and Fe–Cr-Based Alloys

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