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Proceedings Papers

A Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant

Zihao Zheng, Wenxin Qiu, Yang Dai, Jiesheng Min
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A064, August 8–12, 2022
Paper No: ICONE29-93082
https://doi.org/10.1115/ICONE29-93082
View Paper titled, A Proof-of-Concept Application of Fast Fracture Evaluation for the Primary Loop Section in Nuclear Power Plant
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Topics: Brittle fracture, Finite element methods, Fracture (Materials), Fracture (Process), Nuclear power stations, Pipes, Radiation (Physics), Computer software, Engineering standards, Engineers
Proceedings Papers

New Needs of Fracture Mechanic Analysis at Design and Operation Level: Status of French Nuclear Mechanical Codes

Claude Faidy
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A002, July 22–26, 2018
Paper No: ICONE26-81096
https://doi.org/10.1115/ICONE26-81096
View Paper titled, New Needs of Fracture Mechanic Analysis at Design and Operation Level: Status of French Nuclear Mechanical Codes
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Topics: Design, Fracture (Materials), Fracture (Process), Boilers, Brittle fracture, Brittleness, Failure, In-service inspection, Leak-before-break, Manufacturing
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
https://doi.org/10.1115/ICONE25-66447
View Paper titled, RPV Structure Integrity Assessment With Surface Cracks Under PTS
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Topics: Surface cracks, Stress, Transients (Dynamics), Fracture toughness, Cladding systems (Building), Fracture (Materials), Stress concentration, Temperature, Cooling, Finite element methods
Proceedings Papers

The Fracture Behavior of Hydrogen-Charged A508III Low Alloy Steel in the Process of Natural Hydrogen-Escaping

Qian Xiao, Zhanpeng Lu, Junjie Chen, Hao Peng
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A088, July 2–6, 2017
Paper No: ICONE25-67246
https://doi.org/10.1115/ICONE25-67246
View Paper titled, The Fracture Behavior of Hydrogen-Charged A508III Low Alloy Steel in the Process of Natural Hydrogen-Escaping
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Topics: Alloy steel, Fracture (Materials), Fracture (Process), Hydrogen, Brittle fracture, Steel, Tensile strength, Brittleness, Current density, Dislocation density
Proceedings Papers

Effect of Initial and Boundary Conditions on the Formation of Reactor Vessel Pressurized Thermal Shock

Maksym Vyshemirskyi, Aleksander Mazurok, Anatoliy Nosovskyy
Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T16A023, July 29–August 2, 2013
Paper No: ICONE21-15992
https://doi.org/10.1115/ICONE21-15992
View Paper titled, Effect of Initial and Boundary Conditions on the Formation of Reactor Vessel Pressurized Thermal Shock
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Topics: Boundary-value problems, Reactor vessels, Thermal shock, Leakage, Nuclear power stations, Boilers, Brittle fracture, Flow (Dynamics), Fluids, Nuclear power
Proceedings Papers

Creep Strength of Chromium-Containing Conventional and ODS Steels in Oxygen-Controlled Pb at 650°C

Mariya Yurechko, Carsten Schroer, Olaf Wedemeyer, Aleksandr Skrypnik, Jürgen Konys
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, V001T02A008, July 29–August 2, 2013
Paper No: ICONE21-15283
https://doi.org/10.1115/ICONE21-15283
View Paper titled, Creep Strength of Chromium-Containing Conventional and ODS Steels in Oxygen-Controlled Pb at 650°C
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Topics: Creep, Oxygen, Steel, Liquid metals, Brittle fracture, Failure, Martensitic steel, Necking, Risk, Rupture
Proceedings Papers

Factors Promoting Embrittlement of T91 Steel in Liquid Lead-Bismuth Eutectic Alloy

Changqing Ye, Jean-Bernard Vogt, Ingrid Proriol-Serre
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, V001T02A022, July 29–August 2, 2013
Paper No: ICONE21-15642
https://doi.org/10.1115/ICONE21-15642
View Paper titled, Factors Promoting Embrittlement of T91 Steel in Liquid Lead-Bismuth Eutectic Alloy
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Topics: Brittle fracture, Embrittlement, Eutectic alloys, Oxygen, Steel, Brittleness, Heat treating (Metalworking), Liquid metals, Martensitic steel, Mechanical behavior
Proceedings Papers

Missile Safety Analysis of Nuclear Steam Turbine

Rong Chen, Feng Liang, Wen Xiang Hua, Pu Ning Jiang, Xiao Zhong He
Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 787-795, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54434
https://doi.org/10.1115/ICONE20-POWER2012-54434
View Paper titled, Missile Safety Analysis of Nuclear Steam Turbine
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Topics: Missiles, Safety, Steam turbines, Turbines, Failure, Rotors, Damage, Fracture (Materials), Pressure, Brittle fracture
Proceedings Papers

Development of Universal Methodology of Specimen Free Nondestructive Inspection (Control) of Mechanical Properties of NPP Equipment Metal in All Stages of Lifetime

Murat Bakirov, Sergei Chubarov, Igor Frolov, Joerg Gastrock
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 597-603, July 12–16, 2009
Paper No: ICONE17-75606
https://doi.org/10.1115/ICONE17-75606
View Paper titled, Development of Universal Methodology of Specimen Free Nondestructive Inspection (Control) of Mechanical Properties of NPP Equipment Metal in All Stages of Lifetime
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Topics: Mechanical properties, Metals, Nondestructive evaluation, Nuclear power stations, Inspection, Testing, Work hardening, Cycles, Ductility, Irradiation (Radiation exposure)
Proceedings Papers

A Fracture Probability Integral for HFIR Accident Analysis

Shih-Jung Chang
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 281-286, April 25–29, 2004
Paper No: ICONE12-49248
https://doi.org/10.1115/ICONE12-49248
View Paper titled, A Fracture Probability Integral for HFIR Accident Analysis
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Topics: Accidents, Fracture (Materials), Probability, Reactor vessels, Fracture toughness, Simulation, Temperature, Vessels, Brittle fracture, Computation
Proceedings Papers

Experimental Studies on Pb-Bi Flow Technology and Steel Compatibility With Pb-Bi

Masatoshi Kondo, Minoru Takahashi, Susumu Yoshida, Naoki Sawada, Akira Yamada, Koji Hata
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 723-731, April 25–29, 2004
Paper No: ICONE12-49285
https://doi.org/10.1115/ICONE12-49285
View Paper titled, Experimental Studies on Pb-Bi Flow Technology and Steel Compatibility With Pb-Bi
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Topics: Flow (Dynamics), Steel, Pipes, Oxygen, Sensors, Rupture, Strength (Materials), Corrosion, Heat, Steel corrosion
Proceedings Papers

Temperature Dependency of Beremin’s Parameters for 20MnMoNi5-5 Material

B. K. Dutta, S. Guin, M. K. Sahu, M. K. Samal
Proc. ASME. ICONE14, Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy, 255-260, July 17–20, 2006
Paper No: ICONE14-89710
https://doi.org/10.1115/ICONE14-89710
View Paper titled, Temperature Dependency of Beremin’s Parameters for 20MnMoNi5-5 Material
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Topics: Temperature, Fracture (Materials), Stress, Microcracks, Deformation, Finite element analysis, Probability, Brittle fracture, Ductile fracture, Failure