1-15 of 15
Fracture (Materials)
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Journal Articles

High-Performance Manufacturing of Canned Main Coolant Pump — Part II: Reliability Evaluation

Available to Purchase
Accepted Manuscript
M.K. Lei, H.L. Che, Yupeng Li, Bao Zhu, X.P. Zhu, L. Lin, X.P. Lv, M.Q. Li, G.Y. Ma, D.M. Guo
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1098
https://doi.org/10.1115/1.4068596
Published Online: May 3, 2025
View Articletitled, High-Performance Manufacturing of Canned Main Coolant Pump — Part II: Reliability Evaluation
Open the PDF for High-Performance Manufacturing of Canned Main Coolant Pump — Part II: Reliability Evaluation in another window
Topics: Coolants, Manufacturing, Pumps, Reliability, Failure, Density, Engineering prototypes, Cycles, Damage, Design
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
Open the PDF for Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions in another window
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

Free
David L. Y. Louie, San Le, Lindsay N. Gilkey
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
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 Articletitled, Numerical Simulation of Container Breach and Airborne Release of Solids Due to Mechanical Insults
Open the PDF for Numerical Simulation of Container Breach and Airborne Release of Solids Due to Mechanical Insults in another window
Topics: Containers, Damage, Microscale devices, Simulation, Solids, Forklifts, Accidents, Fracture (Materials)
Journal Articles

Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage

Available to Purchase
Sandip Ghosh, Samir Kumar Saha
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
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 Articletitled, Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage
Open the PDF for Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage in another window
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

Available to Purchase
J. Veselá, P. Mareš, P. Zahrádka, J. Patera
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
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 Articletitled, Evaluation of Steam Turbine Blades Surface Cracks Detectability by Nondestructive Methods
Open the PDF for Evaluation of Steam Turbine Blades Surface Cracks Detectability by Nondestructive Methods in another window
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

Available to Purchase
Andrew Oussoren, Paul Chan, Diane Wowk, Andrew Prudil
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
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 Articletitled, Toward a Mechanistic Model of Stress Corrosion Cracking in PHWR Fuel Sheaths
Open the PDF for Toward a Mechanistic Model of Stress Corrosion Cracking in PHWR Fuel Sheaths in another window
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

Available to Purchase
Kevin (Wenhai) Li, Michel Gaudet
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
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 Articletitled, High Spatial Resolution Crack Monitoring in Concrete Structures Using a Distributed Fiber Optic Sensor
Open the PDF for High Spatial Resolution Crack Monitoring in Concrete Structures Using a Distributed Fiber Optic Sensor in another window
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

Available to Purchase
A. K. Nayak, Mukesh Kumar, Sumit V. Prasad, V. Jain, D. K. Chandraker
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
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 Articletitled, Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor
Open the PDF for Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor in another window
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

Available to Purchase
Anna Hojna, Mariia Zimina, Lucia Rozumova
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
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 Articletitled, Effect of the Surface Grinding on the Environmentally Assisted Crack Initiation of 316 L Steel in Simulated Pressurized Water Reactor Water
Open the PDF for Effect of the Surface Grinding on the Environmentally Assisted Crack Initiation of 316 L Steel in Simulated Pressurized Water Reactor Water in another window
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

Available to Purchase
Akihiro Mano, Yoshihito Yamaguchi, Jinya Katsuyama, Yinsheng Li
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
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 Articletitled, Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP With Regard to PWSCC
Open the PDF for Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP With Regard to PWSCC in another window
Topics: Failure, Fracture (Materials), Leakage, Pipes, Probability, Nondestructive evaluation, Stress
Journal Articles

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

Available to Purchase
Anna Hojna, Fosca Di Gabriele, Michal Chocholousek, Zbynek Spirit, Lucia Rozumova
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
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 Articletitled, Study of Crack Initiation of 15-15Ti Austenitic Steel in Liquid PbBi
Open the PDF for Study of Crack Initiation of 15-15Ti Austenitic Steel in Liquid PbBi in another window
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

Available to Purchase
Waleed Ishaque
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
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 Articletitled, Use of Irradiated Fracture Toughness Values in Nuclear Vessel and Component Design Specifications for Fitness-For-Service Analysis Using the Unified Curve Method
Open the PDF for Use of Irradiated Fracture Toughness Values in Nuclear Vessel and Component Design Specifications for Fitness-For-Service Analysis Using the Unified Curve Method in another window
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

Available to Purchase
Toru Kitagaki, Takanori Hoshino, Kimihiko Yano, Nobuo Okamura, Hiroshi Ohara, Tetsuo Fukasawa, Kenji Koizumi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
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 Articletitled, Mechanical Properties of Cubic (U,Zr)O 2
Open the PDF for Mechanical Properties of Cubic (U,Zr)O 2 in another window
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

Available to Purchase
Bin Gong, Yanping Huang, E. Jiang, Yongfu Zhao, Weiwei Liu, Zhiru Zhou
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
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 Articletitled, Effect of Oxidation Chemistry of Supercritical Water on Stress Corrosion Cracking of Austenitic Steels
Open the PDF for Effect of Oxidation Chemistry of Supercritical Water on Stress Corrosion Cracking of Austenitic Steels in another window
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

Available to Purchase
Shigeru Takaya, Tai Asayama, Yoshio Kamishima, Hideo Machida, Daigo Watanabe, Satoru Nakai, Masaki Morishita
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
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 Articletitled, Application of the System Based Code Concept to the Determination of In-Service Inspection Requirements
Open the PDF for Application of the System Based Code Concept to the Determination of In-Service Inspection Requirements in another window
Topics: Creep, Design, Failure, Fatigue, Fracture (Materials), In-service inspection, Probability, Reliability, Safety, Stress