1-20 of 48
Fracture toughness
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
Proceedings Papers

Study on the Manufacturing Process of Large Super Alloy X-750 Forgings for Nuclear Equipment

Mei-fang Chen, Sheng-qiang Cao, Kai Dong
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A019, August 8–12, 2022
Paper No: ICONE29-91791
DOI: https://doi.org/10.1115/ICONE29-91791
View Paper
PDF
Topics: Alloys, Forging, Forgings (Products), Manufacturing, Springs, Temperature, Grain size, Annealing, Creep, Fracture (Materials)
Proceedings Papers

Research and Development of SA508Gr.4N Steel Ultra-Thick Forgings With High Strength and Toughness for Nuclear Engineering

Dongxu Du, Deli Zhao, Liguo Ren, Wenhui Zhang, Jiaju Li, Xikou He
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A031, August 8–12, 2022
Paper No: ICONE29-92329
DOI: https://doi.org/10.1115/ICONE29-92329
View Paper
PDF
Topics: Embrittlement, Forgings (Products), Fracture toughness, Industrial research, Irradiation (Radiation exposure), Nuclear engineering, Steel
Proceedings Papers

Study on the Thermal-Mechanical Performance of SiC Composites Cladding Under Multiple Conditions

Chunyu Yin
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T05A013, August 4–5, 2020
Paper No: ICONE2020-16793
DOI: https://doi.org/10.1115/ICONE2020-16793
View Paper
PDF
Topics: Cladding systems (Building), Composite materials, Failure, Hoop stress, Fracture toughness, Probability, Temperature, Accidents, Brittleness, Ceramics
Proceedings Papers

Evaluation of Irradiation Embrittlement of the Weld Metals in the Chinese RPV

Yupeng Cao, Yinbiao He, Yifeng Huang, Binxi Wang, Yan Yu, Hui Li, Hu Hui
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T09A003, August 4–5, 2020
Paper No: ICONE2020-16261
DOI: https://doi.org/10.1115/ICONE2020-16261
View Paper
PDF
Topics: Embrittlement, Irradiation (Radiation exposure), Metals, Forging, Mechanical properties, China, Damage, Design, Fluence (Radiation measurement), Fracture toughness
Proceedings Papers

Probability of Rupture for WWER-1000 Main Piping

Yaroslav Dubyk, Maksym Zarazovskii, Sergii Ageiev, Vladislav Filonov
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A014, August 4–5, 2020
Paper No: ICONE2020-16897
DOI: https://doi.org/10.1115/ICONE2020-16897
View Paper
PDF
Topics: Leakage, Pipes, Probability, Rupture, Stress, Fracture (Materials), Accounting, Flow (Dynamics), Fracture toughness, Nuclear power stations
Proceedings Papers

Determination of Fracture Toughness From Small Punch Test Using Inverse Finite Element Method for In-Service Equipment

Kaishu Guan, Tong Xu, Linling Guo, Mingxue Fu, Huadong Zhu
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T01A034, July 2–6, 2017
Paper No: ICONE25-67406
DOI: https://doi.org/10.1115/ICONE25-67406
View Paper
PDF
Topics: Finite element methods, Fracture toughness, Displacement, Stress, Pressure equipment, Mechanical properties, Databases, Mechanical testing, Artificial neural networks, Computer simulation
Proceedings Papers

RPV Structure Integrity Assessment With Surface Cracks Under PTS

Wei Lu, Zheng He
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A048, July 2–6, 2017
Paper No: ICONE25-66447
DOI: https://doi.org/10.1115/ICONE25-66447
View Paper
PDF
Topics: Surface cracks, Stress, Transients (Dynamics), Fracture toughness, Cladding systems (Building), Fracture (Materials), Stress concentration, Temperature, Cooling, Finite element methods
Proceedings Papers

Effects of Neutron Irradiation on the Mechanical and Electromagnetic Properties of Reactor Pressure Vessel Steels

Li Chengliang, Shu Guogang, Chen Jun, Liu Yi, Liu Wei, Hu Yichuan, Duan Yuangang, Liu Feihua
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A013, July 2–6, 2017
Paper No: ICONE25-66464
DOI: https://doi.org/10.1115/ICONE25-66464
View Paper
PDF
Topics: Irradiation (Radiation exposure), Neutrons, Reactor vessels, Steel, Damage, Electrical resistivity, Ductility, Failure mechanisms, Fracture toughness, Magnetization
Proceedings Papers

Transient Heat Transfer for Helium Gas Flowing Over a Horizontal Cylinder Under Flow Decay Conditions

Qiusheng Liu, Li Wang, Makoto Shibahara, Katsuya Fukuda
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A062, June 26–30, 2016
Paper No: ICONE24-60783
DOI: https://doi.org/10.1115/ICONE24-60783
View Paper
PDF
Topics: Cylinders, Flow (Dynamics), Helium, Transient heat transfer, Temperature, Very high temperature reactors, Coolants, Heat, Fuels, Transients (Dynamics)
Proceedings Papers

Fracture Resistance of Cast Austenitic Stainless Steels

Y. Chen, W-Y. Chen, A. S. Rao, Z. Li, Y. Yang, B. Alexandreanu, K. Natesan
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T03A022, June 26–30, 2016
Paper No: ICONE24-60736
DOI: https://doi.org/10.1115/ICONE24-60736
View Paper
PDF
Topics: Fracture (Materials), Stainless steel, Neutrons, Irradiation (Radiation exposure), Ferrites (Magnetic materials), Fracture toughness, Alloys, Embrittlement, Light water reactors, Corrosion resistance
Proceedings Papers

Character of Liquid Metal Embrittlement of the Steel T91 in Contact With Lead-Bismuth Eutectic

Anna Hojna, Fosca Di Gabriele, Jakub Klecka
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T02A006, July 7–11, 2014
Paper No: ICONE22-30322
DOI: https://doi.org/10.1115/ICONE22-30322
View Paper
PDF
Topics: Embrittlement, Liquid metals, Steel, Fracture (Materials), Fracture toughness, ASTM standards, Martensitic steel
Proceedings Papers

Japanese Codes and Standards for Dual Purpose Metal Casks for Spent Nuclear Fuel

Toshiari Saegusa, Makoto Hirose, Norikazu Irie, Masashi Shimizu
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T07A009, July 7–11, 2014
Paper No: ICONE22-30696
DOI: https://doi.org/10.1115/ICONE22-30696
View Paper
PDF
Topics: Engineering standards, Metals, Spent nuclear fuels, Storage, Stress, Containment vessels, Japan Society of Mechanical Engineers, Safety, Design, Nuclear power stations
Proceedings Papers

3D Calculations of PWR Vessels Neutron Fluence With EFLUVE 3D Code

Cécile-Aline Gosmain, Sylvain Rollet, Damien Schmitt
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A035, July 29–August 2, 2013
Paper No: ICONE21-16316
DOI: https://doi.org/10.1115/ICONE21-16316
View Paper
PDF
Topics: Fluence (Radiation measurement), Neutrons, Pressurized water reactors, Vessels, Neutron sources, Surveillance, Chemical kinetics, Pressure vessels, Dosimeters, Dosimetry
Proceedings Papers

Prospect of MAO Technology Application in Nuclear Power Industry

Zheng Zhao, Beibei Feng, Xingtuan Yang, Yanfei Sun
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A019, July 29–August 2, 2013
Paper No: ICONE21-15435
DOI: https://doi.org/10.1115/ICONE21-15435
View Paper
PDF
Topics: Nuclear industry, Alloys, Aluminum, Cladding systems (Building), Corrosion, Fuels, Nuclear reactors, Accidents, Aerospace industry, Aviation
Proceedings Papers

An Experimental Study on Fracture Toughness of a Fine-Grained Isotropic Graphite

Hongtao Wang, Libin Sun, Haitao Wang, Li Shi, Zhensheng Zhang
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 175-179, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-55008
DOI: https://doi.org/10.1115/ICONE20-POWER2012-55008
View Paper
PDF
Topics: Fracture toughness, Graphite
Proceedings Papers

Fracture Toughness of Nuclear Graphite NBG-18

Haiyan Li, Gyanender Singh, Young Heo, Lianshan Lin, Alex Fok
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 393-397, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54581
DOI: https://doi.org/10.1115/ICONE20-POWER2012-54581
View Paper
PDF
Topics: Fracture toughness, Graphite
Proceedings Papers

Underwater Laser Beam Welding for Nuclear Reactors

Masaki Yoda, Masataka Tamura, Takeshi Fukuda, Katsunori Shiihara, Kazuo Sudo, Takeshi Maehara, Yasuo Morishima, Hiromi Kato, Hiroya Ichikawa
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 191-195, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54836
DOI: https://doi.org/10.1115/ICONE20-POWER2012-54836
View Paper
PDF
Topics: Laser welding, Nuclear reactors, Welding, Welding equipment, Maintenance, Nozzles, Nuclear power stations, Pressurized water reactors, Temperature, Alloy steel
Proceedings Papers

EFLUVE3D Code: A 3D Tool for the Neutron Fluence Calculations on Pressurized Water Reactor Vessels

Cécile-Aline Gosmain, Sylvain Rollet, Damien Schmitt
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 481-489, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54965
DOI: https://doi.org/10.1115/ICONE20-POWER2012-54965
View Paper
PDF
Topics: Fluence (Radiation measurement), Neutrons, Pressurized water reactors, Vessels, Neutron sources, Surveillance, Dosimeters, Pressure vessels, Chemical kinetics, Dosimetry
Proceedings Papers

Fracture Strength Estimation of SiC Block for IS Process

Hiroaki Takegami, Atsuhiko Terada, Kaoru Onuki, Ryutaro Hino
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 3, 93-98, May 17–21, 2010
Paper No: ICONE18-29267
DOI: https://doi.org/10.1115/ICONE18-29267
View Paper
PDF
Topics: Fracture toughness, Ceramics, Reliability, Design, Economics , Heat exchangers, Hydrogen, Hydrogen production, Nuclear power, Sulfur
Proceedings Papers

Corrosion Properties of Welded Ferritic-Martensitic Steels in Liquid Lead-Bismuth at 600C

Asril Pramutadi Andi Mustari, Minoru Takahashi
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 229-235, May 17–21, 2010
Paper No: ICONE18-29927
DOI: https://doi.org/10.1115/ICONE18-29927
View Paper
PDF
Topics: Corrosion, Steel, Base metals, Diffusion (Physics), Cross section (Physics), Electric current, Electrical conductance, Electron beam welding, Fracture toughness, Gas tungsten arc welding