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Proceedings Papers

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

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
Paper No: ICONE2020-16668
DOI: https://doi.org/10.1115/ICONE2020-16668
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Topics: Fatigue analysis, Stress analysis (Engineering), Thermal shock
Proceedings Papers

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

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
Paper No: ICONE2020-16872
DOI: https://doi.org/10.1115/ICONE2020-16872
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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

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
Paper No: ICONE2020-16773
DOI: https://doi.org/10.1115/ICONE2020-16773
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Topics: Alloys, Hardening, Metals, Nickel, Stress, Stress analysis (Engineering), Welding
Proceedings Papers

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

Claude Faidy
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A001, July 22–26, 2018
Paper No: ICONE26-81095
DOI: https://doi.org/10.1115/ICONE26-81095
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Topics: Design, Pressure vessels, Stress, Failure mechanisms, Materials properties, Stress analysis (Engineering), Collapse, Constitutive equations, Failure, Fatigue
Proceedings Papers

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

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
Paper No: ICONE26-81468
DOI: https://doi.org/10.1115/ICONE26-81468
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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

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
Paper No: ICONE26-82242
DOI: https://doi.org/10.1115/ICONE26-82242
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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

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
Paper No: ICONE26-81279
DOI: https://doi.org/10.1115/ICONE26-81279
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Topics: Boilers, Failure, Probability, Stress, Nonlinear systems, Nuclear reactor coolants, Plasticity, Safety, Seismic analysis, Stress analysis (Engineering)
Proceedings Papers

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

Jian Zhang, Yongde Zuo, Xingjiang Chen, Qinghong Zhang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A055, July 2–6, 2017
Paper No: ICONE25-66591
DOI: https://doi.org/10.1115/ICONE25-66591
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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

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
Paper No: ICONE25-66814
DOI: https://doi.org/10.1115/ICONE25-66814
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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

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
Paper No: ICONE25-66999
DOI: https://doi.org/10.1115/ICONE25-66999
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Topics: In-service inspection, Pressurized water reactors, Fracture (Materials), Inspection, ASME Standards, Failure, Probes, Signals, Testing, Water
Proceedings Papers

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

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
Paper No: ICONE25-67136
DOI: https://doi.org/10.1115/ICONE25-67136
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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

Stress Analysis of the Canned Nuclear Coolant Pump Based on FSI

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
Paper No: ICONE22-30587
DOI: https://doi.org/10.1115/ICONE22-30587
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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

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
Paper No: ICONE22-30546
DOI: https://doi.org/10.1115/ICONE22-30546
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Topics: Modeling, Finite element methods, Finite element model, Stress, Vessels, Accidents, Creep, Erosion, Errors, Numerical analysis
Proceedings Papers

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

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
Paper No: ICONE22-30686
DOI: https://doi.org/10.1115/ICONE22-30686
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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

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
Paper No: ICONE22-30134
DOI: https://doi.org/10.1115/ICONE22-30134
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Topics: Fuels, Pressure, Steam, Stress analysis (Engineering), Temperature, Water, Computer software, Coolants, Design, Displacement
Proceedings Papers

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

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
Paper No: ICONE21-15735
DOI: https://doi.org/10.1115/ICONE21-15735
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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

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
Paper No: ICONE21-15273
DOI: https://doi.org/10.1115/ICONE21-15273
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Topics: Pipes, Stress, Computer simulation, Defense industry, Energy budget (Physics), Hydrodynamics, Leak-before-break, Nuclear design, Piping systems, Regulations
Proceedings Papers

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

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
Paper No: ICONE21-15574
DOI: https://doi.org/10.1115/ICONE21-15574
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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

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
Paper No: ICONE21-15853
DOI: https://doi.org/10.1115/ICONE21-15853
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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

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
Paper No: ICONE21-16313
DOI: https://doi.org/10.1115/ICONE21-16313
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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