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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

Publisher: ASME

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

Numerical Simulation of Container Breach and Airborne Release of Solids Due to Mechanical Insults

David L. Y. Louie, San Le, Lindsay N. Gilkey

Publisher: ASME

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031901.

Paper No: NERS-19-1171

https://doi.org/10.1115/1.4050212

Published Online: April 16, 2021

View Article titled, Numerical Simulation of Container Breach and Airborne Release of Solids Due to Mechanical Insults

Topics: Containers, Damage, Microscale devices, Simulation, Solids, Forklifts, Accidents, Fracture (Materials)

Journal Articles

Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage

Sandip Ghosh, Samir Kumar Saha

Publisher: ASME

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034503.

Paper No: NERS-20-1012

https://doi.org/10.1115/1.4048477

Published Online: March 16, 2021

View Article titled, Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage

Topics: Flow (Dynamics), Leakage, Pipes, Simulation, Subcooling, Flashing, Coolants, Fracture (Materials), Modeling, Vapors

Journal Articles

Evaluation of Steam Turbine Blades Surface Cracks Detectability by Nondestructive Methods

J. Veselá, P. Mareš, P. Zahrádka, J. Patera

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2021, 7(2): 024504.

Paper No: NERS-20-1101

https://doi.org/10.1115/1.4048479

Published Online: November 16, 2020

View Article titled, Evaluation of Steam Turbine Blades Surface Cracks Detectability by Nondestructive Methods

Topics: Blades, Fracture (Materials), Steam turbines, Surface cracks, Testing, Ultrasonic testing, Corrosion, Turbine blades, Magnetic particles, Eddies (Fluid dynamics)

Journal Articles

Toward a Mechanistic Model of Stress Corrosion Cracking in PHWR Fuel Sheaths

Andrew Oussoren, Paul Chan, Diane Wowk, Andrew Prudil

Publisher: ASME

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011604.

Paper No: NERS-19-1018

https://doi.org/10.1115/1.4048120

Published Online: October 5, 2020

View Article titled, Toward a Mechanistic Model of Stress Corrosion Cracking in PHWR Fuel Sheaths

Topics: Failure, Fracture (Materials), Fuels, Nuclear fission, Diffusion (Physics)

Journal Articles

High Spatial Resolution Crack Monitoring in Concrete Structures Using a Distributed Fiber Optic Sensor

Kevin (Wenhai) Li, Michel Gaudet

Publisher: ASME

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011111.

Paper No: NERS-19-1056

https://doi.org/10.1115/1.4045124

Published Online: November 8, 2019

View Article titled, High Spatial Resolution Crack Monitoring in Concrete Structures Using a Distributed Fiber Optic Sensor

Topics: Concretes, Diffraction gratings, Fiber optic sensors, Fibers, Fracture (Materials), Resolution (Optics), Sensors, Wavelength, Fiber Bragg gratings, Concrete beams

Journal Articles

Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor

A. K. Nayak, Mukesh Kumar, Sumit V. Prasad, V. Jain, D. K. Chandraker

Publisher: ASME

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041203.

Paper No: NERS-18-1079

https://doi.org/10.1115/1.4042852

Published Online: July 19, 2019

View Article titled, Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor

Topics: Heat, Test facilities, Water, Cavities, Earthquakes, Heat sinks, Boiling water reactors, Flow (Dynamics), Fukushima nuclear disaster, Japan, 2011, Fracture (Materials)

Journal Articles

Effect of the Surface Grinding on the Environmentally Assisted Crack Initiation of 316 L Steel in Simulated Pressurized Water Reactor Water

Anna Hojna, Mariia Zimina, Lucia Rozumova

Publisher: ASME

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030909.

Paper No: NERS-19-1017

https://doi.org/10.1115/1.4043099

Published Online: May 10, 2019

View Article titled, Effect of the Surface Grinding on the Environmentally Assisted Crack Initiation of 316 L Steel in Simulated Pressurized Water Reactor Water

Topics: Fracture (Materials), Polishing, Pressurized water reactors, Steel, Stress, Water, Fracture (Process), Testing, Grinding

Journal Articles

Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP With Regard to PWSCC

Akihiro Mano, Yoshihito Yamaguchi, Jinya Katsuyama, Yinsheng Li

Publisher: ASME

ASME J of Nuclear Rad Sci. July 2019, 5(3): 031501.

Paper No: NERS-17-1220

https://doi.org/10.1115/1.4042115

Published Online: May 3, 2019

View Article titled, Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP With Regard to PWSCC

Topics: Failure, Fracture (Materials), Leakage, Pipes, Probability, Nondestructive evaluation, Stress

Journal Articles

Study of Crack Initiation of 15-15Ti Austenitic Steel in Liquid PbBi

Anna Hojna, Fosca Di Gabriele, Michal Chocholousek, Zbynek Spirit, Lucia Rozumova

Publisher: ASME

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030902.

Paper No: NERS-18-1031

https://doi.org/10.1115/1.4041564

Published Online: April 16, 2019

View Article titled, Study of Crack Initiation of 15-15Ti Austenitic Steel in Liquid PbBi

Topics: Fracture (Materials), Polishing, Stress, Steel

Journal Articles

Use of Irradiated Fracture Toughness Values in Nuclear Vessel and Component Design Specifications for Fitness-For-Service Analysis Using the Unified Curve Method

Waleed Ishaque

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020911.

Paper No: NERS-18-1062

https://doi.org/10.1115/1.4042498

Published Online: March 15, 2019

View Article titled, Use of Irradiated Fracture Toughness Values in Nuclear Vessel and Component Design Specifications for Fitness-For-Service Analysis Using the Unified Curve Method

Topics: American Petroleum Institute, Fracture (Materials), Fracture toughness, Junctions, Nozzles, Stress, Vessels, Design, Fitness-for-service, Steel

Journal Articles

Mechanical Properties of Cubic (U,Zr)O 2

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

Publisher: ASME

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

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

Publisher: ASME

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

Topics: Chemistry, Fracture (Materials), Steel, Stress corrosion cracking, Water, Water chemistry, Oxidation, Temperature, Supercritical water reactors, Oxygen

Journal Articles

Application of the System Based Code Concept to the Determination of In-Service Inspection Requirements

Shigeru Takaya, Tai Asayama, Yoshio Kamishima, Hideo Machida, Daigo Watanabe, Satoru Nakai, Masaki Morishita

Publisher: ASME

ASME J of Nuclear Rad Sci. January 2015, 1(1): 011004.

Paper No: NERS-14-1020

https://doi.org/10.1115/1.4026392

Published Online: February 9, 2015

View Article titled, Application of the System Based Code Concept to the Determination of In-Service Inspection Requirements

Topics: Creep, Design, Failure, Fatigue, Fracture (Materials), In-service inspection, Probability, Reliability, Safety, Stress

Journal citation

NARROW

Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions

Numerical Simulation of Container Breach and Airborne Release of Solids Due to Mechanical Insults

Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage

Evaluation of Steam Turbine Blades Surface Cracks Detectability by Nondestructive Methods

Toward a Mechanistic Model of Stress Corrosion Cracking in PHWR Fuel Sheaths

High Spatial Resolution Crack Monitoring in Concrete Structures Using a Distributed Fiber Optic Sensor

Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor

Effect of the Surface Grinding on the Environmentally Assisted Crack Initiation of 316 L Steel in Simulated Pressurized Water Reactor Water

Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP With Regard to PWSCC

Study of Crack Initiation of 15-15Ti Austenitic Steel in Liquid PbBi

Use of Irradiated Fracture Toughness Values in Nuclear Vessel and Component Design Specifications for Fitness-For-Service Analysis Using the Unified Curve Method

Mechanical Properties of Cubic (U,Zr)O 2

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

Application of the System Based Code Concept to the Determination of In-Service Inspection Requirements

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