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Proceedings Papers

Stress Analysis of the Pressurized-Water Reactor Control Rod Under Operating Conditions

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Leo A. Carrilho
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, V001T05A015, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16872
https://doi.org/10.1115/ICONE2020-16872
View Paper titled, Stress Analysis of the Pressurized-Water Reactor Control Rod Under Operating Conditions
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Topics: Pressurized water reactors, Stress, Stress analysis (Engineering), Water, Cladding systems (Building), Finite element model, Fluence (Radiation measurement), Temperature, Thermal expansion, Coolants
Proceedings Papers

Investigation of Hardening Law on Welding Residual Stress Analysis for Nickel Based Alloy 82 Weld Metal

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Mitsuru Ejiri, Teppei Kubota, Yukihiro Soga, Nozomi Nishihara, Nobuyoshi Yanagida, Hiroomi Katou, Tomoyuki Arashiba, Wataru Taniura
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, V001T06A023, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16773
https://doi.org/10.1115/ICONE2020-16773
View Paper titled, Investigation of Hardening Law on Welding Residual Stress Analysis for Nickel Based Alloy 82 Weld Metal
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Topics: Alloys, Hardening, Metals, Nickel, Stress, Stress analysis (Engineering), Welding
Proceedings Papers

Stress Analysis of the Lower Head of Central Measuring Shroud Under Thermal Striping and Thermal Shock Conditions

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Shu Zheng, Daogang Lu, Qiong Cao
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, V001T06A019, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16668
https://doi.org/10.1115/ICONE2020-16668
View Paper titled, Stress Analysis of the Lower Head of Central Measuring Shroud Under Thermal Striping and Thermal Shock Conditions
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Topics: Fatigue analysis, Stress analysis (Engineering), Thermal shock
Proceedings Papers

Strength Limit of Thimble Tube With Material Plasticity Under Bending Moment and Axial Compression Force

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Hisashi Koike, Masaji Mori, Daisuke Fujiwara, Takashi Shimomura
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A020, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81468
https://doi.org/10.1115/ICONE26-81468
View Paper titled, Strength Limit of Thimble Tube With Material Plasticity Under Bending Moment and Axial Compression Force
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Topics: ASME Standards, Compression, Earthquakes, Evaluation methods, Fuels, Manufacturing, Plasticity, Plastics, Pressurized water reactors, Stress
Proceedings Papers

Preliminary Development of a TRISO Fuel Performance Analysis Code: FFAT

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Jian Li, Ding She, Lei Shi, Jing Zhao
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A046, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82242
https://doi.org/10.1115/ICONE26-82242
View Paper titled, Preliminary Development of a TRISO Fuel Performance Analysis Code: FFAT
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Topics: Fuels, Particulate matter, Failure, Very high temperature reactors, Accidents, Equipment performance, Gas cooled reactors, High temperature, Pressure vessels, Probability
Proceedings Papers

Study on Methods for HCLPF Value of Nonlinear Supports System of Steam Generator

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Feng-chun Cai, Xian-hui Ye, Qian Huang, Wenzheng Zhang
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A010, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81279
https://doi.org/10.1115/ICONE26-81279
View Paper titled, Study on Methods for HCLPF Value of Nonlinear Supports System of Steam Generator
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Topics: Boilers, Failure, Probability, Stress, Nonlinear systems, Nuclear reactor coolants, Plasticity, Safety, Seismic analysis, Stress analysis (Engineering)
Proceedings Papers

Nonlinear Analysis in Pressure Vessel Design Codes: Recommendations for Codified Rules Improvements

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Claude Faidy
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A001, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81095
https://doi.org/10.1115/ICONE26-81095
View Paper titled, Nonlinear Analysis in Pressure Vessel Design Codes: Recommendations for Codified Rules Improvements
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Topics: Design, Pressure vessels, Stress, Failure mechanisms, Materials properties, Stress analysis (Engineering), Collapse, Constitutive equations, Failure, Fatigue
Proceedings Papers

Fluid-Structure Interaction Numerical Analysis of the Spent Fuel Pool and Storage Racks Under Earthquake

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Ling Yun, Li Lei, Xue Rongjun, Qian Hao, Ge Honghui, Shang Ziduan
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A083, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67136
https://doi.org/10.1115/ICONE25-67136
View Paper titled, Fluid-Structure Interaction Numerical Analysis of the Spent Fuel Pool and Storage Racks Under Earthquake
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Topics: Earthquakes, Fluid structure interaction, Numerical analysis, Spent nuclear fuels, Storage, Finite element analysis, Water, Sloshing, Computational fluid dynamics, Concretes
Proceedings Papers

Research on the Structure Integrity Analysis of Flywheel of Reactor Coolant Pump in Nuclear Power Plant

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Jian Zhang, Yongde Zuo, Xingjiang Chen, Qinghong Zhang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A055, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66591
https://doi.org/10.1115/ICONE25-66591
View Paper titled, Research on the Structure Integrity Analysis of Flywheel of Reactor Coolant Pump in Nuclear Power Plant
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Topics: Flywheels, Nuclear power stations, Nuclear reactor coolants, Pumps, Failure, Stress, Damage, Design, Failure analysis, Kinetic energy
Proceedings Papers

Stress Analysis of Three-Layer SiC Cladding for PWRs

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Weiping Lan, Dachao Lin, Zulong Hao, Fenglei Niu
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A032, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66814
https://doi.org/10.1115/ICONE25-66814
View Paper titled, Stress Analysis of Three-Layer SiC Cladding for PWRs
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Topics: Cladding systems (Building), Pressurized water reactors, Stress analysis (Engineering), Fuels, Composite materials, Finite element analysis, Stress concentration, Temperature distribution, Coating processes, Coatings
Proceedings Papers

In-Service Inspection Technology Research on CANOPY Seal Weld of Control Rod Drive Mechanism in PWR

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Zhou Lifeng, Cheng Zhaoyu, Cai Jiafan, Tang Yi
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, V001T01A028, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66999
https://doi.org/10.1115/ICONE25-66999
View Paper titled, In-Service Inspection Technology Research on CANOPY Seal Weld of Control Rod Drive Mechanism in PWR
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Topics: In-service inspection, Pressurized water reactors, Fracture (Materials), Inspection, ASME Standards, Failure, Probes, Signals, Testing, Water
Proceedings Papers

The Surge Line Stress Analysis Model Setup With the Consideration of Thermal Stratification

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Jianjun Wang, Zengfang Ge, Zhongning Sun, Changqi Yan
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T10A029, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30686
https://doi.org/10.1115/ICONE22-30686
View Paper titled, The Surge Line Stress Analysis Model Setup With the Consideration of Thermal Stratification
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Topics: Stress analysis (Engineering), Surges, Thermal stratification, Stress, Transients (Dynamics), Heat, Temperature, Pressurized water reactors, Computational fluid dynamics, Design
Proceedings Papers

Materials and Stress Analysis of Fuel-Channel of a Generic 1200-MW el Pressure-Channel Reactor With Nuclear Steam Reheat

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Rand Abdullah, Matthew Baldock, Andrei Vincze, Khalil Sidawi, Igor Pioro
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A016, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30134
https://doi.org/10.1115/ICONE22-30134
View Paper titled, Materials and Stress Analysis of Fuel-Channel of a Generic 1200-MW el Pressure-Channel Reactor With Nuclear Steam Reheat
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Topics: Fuels, Pressure, Steam, Stress analysis (Engineering), Temperature, Water, Computer software, Coolants, Design, Displacement
Proceedings Papers

Stress Analysis of the Canned Nuclear Coolant Pump Based on FSI

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Zhang Ji-Ge, Zhu Yue
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T10A023, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30587
https://doi.org/10.1115/ICONE22-30587
View Paper titled, Stress Analysis of the Canned Nuclear Coolant Pump Based on FSI
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Topics: Coolants, Fluid structure interaction, Pumps, Stress analysis (Engineering), Impellers, Stress, Blades, Flow (Dynamics), Fracture (Materials), Fracture (Process)
Proceedings Papers

End-to-End Technology of Modeling a Melt-Structure Interaction During IVMR in VVER With HEFEST-URAN Toolkit

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A. S. Filippov, N. I. Drobyshevsky, D. D. Kamenskay, A. E. Kisselev, E. V. Moiseenko
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A020, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30546
https://doi.org/10.1115/ICONE22-30546
View Paper titled, End-to-End Technology of Modeling a Melt-Structure Interaction During IVMR in VVER With HEFEST-URAN Toolkit
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Topics: Modeling, Finite element methods, Finite element model, Stress, Vessels, Accidents, Creep, Erosion, Errors, Numerical analysis
Proceedings Papers

The Reliability Prediction of HTR’s Graphite Component in Various Temperature and Neutron Dose Levels

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Xiang Fang, Haitao Wang, Xingtuan Yang, Suyuan Yu
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A028, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15574
https://doi.org/10.1115/ICONE21-15574
View Paper titled, The Reliability Prediction of HTR’s Graphite Component in Various Temperature and Neutron Dose Levels
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Topics: Graphite, Neutrons, Reliability, Temperature, Bricks, High temperature, Irradiation (Radiation exposure), Stress, Constitutive equations, Failure
Proceedings Papers

The Measurement of the High Temperature Sodium Pipe in CEFR

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Huajin Yu, Long Tang, Min Qi, Yuanwu Ye
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A025, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15853
https://doi.org/10.1115/ICONE21-15853
View Paper titled, The Measurement of the High Temperature Sodium Pipe in CEFR
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Topics: High temperature, Pipes, Sodium, Displacement measurement, Displacement, Fast neutron reactors, Accidents, China, Circuits, Cooling systems
Proceedings Papers

Stress Analysis and Assess for Nuclear Pipes of Class 1 Based on PIPESTRESS

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Rui Liu, Tie-ping Li, Ming-yu Wang
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A046, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16313
https://doi.org/10.1115/ICONE21-16313
View Paper titled, Stress Analysis and Assess for Nuclear Pipes of Class 1 Based on PIPESTRESS
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Topics: Pipes, Stress analysis (Engineering), Computer software, Coolants, Cooling, Fatigue analysis, Finite element analysis, High pressure (Physics), High temperature, Nuclear power
Proceedings Papers

CFD Analysis of Thermal Stratification Phenomena in the RNS Suction Line of a Gen-III Nuclear Power Plant

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Yan Li, Daogang Lu, Zhigang Wang, Jian Wu, Fengyun Yu
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T10A025, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15735
https://doi.org/10.1115/ICONE21-15735
View Paper titled, CFD Analysis of Thermal Stratification Phenomena in the RNS Suction Line of a Gen-III Nuclear Power Plant
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Topics: Computational fluid dynamics, Nuclear power stations, Suction, Thermal stratification, Leakage, Temperature, Flow (Dynamics), Pipes, Density, Heat
Proceedings Papers

Analysis of Dynamic Effects Associated With Postulated Breaks of Piping

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Manqing Qin, Xinghua Li, Jicheng Zhao
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, V001T01A016, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15273
https://doi.org/10.1115/ICONE21-15273
View Paper titled, Analysis of Dynamic Effects Associated With Postulated Breaks of Piping
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Topics: Pipes, Stress, Computer simulation, Defense industry, Energy budget (Physics), Hydrodynamics, Leak-before-break, Nuclear design, Piping systems, Regulations