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Stress analysis (Engineering)
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Proceedings Papers
Stress Analysis of the Pressurized-Water Reactor Control Rod Under Operating Conditions
Available to Purchase
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
Proceedings Papers
Investigation of Hardening Law on Welding Residual Stress Analysis for Nickel Based Alloy 82 Weld Metal
Available to PurchaseMitsuru 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
Proceedings Papers
Stress Analysis of the Lower Head of Central Measuring Shroud Under Thermal Striping and Thermal Shock Conditions
Available to Purchase
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
Proceedings Papers
Strength Limit of Thimble Tube With Material Plasticity Under Bending Moment and Axial Compression Force
Available to Purchase
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
Proceedings Papers
Preliminary Development of a TRISO Fuel Performance Analysis Code: FFAT
Available to Purchase
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
Proceedings Papers
Study on Methods for HCLPF Value of Nonlinear Supports System of Steam Generator
Available to Purchase
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
Proceedings Papers
Nonlinear Analysis in Pressure Vessel Design Codes: Recommendations for Codified Rules Improvements
Available to Purchase
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
Proceedings Papers
Fluid-Structure Interaction Numerical Analysis of the Spent Fuel Pool and Storage Racks Under Earthquake
Available to Purchase
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
Proceedings Papers
Research on the Structure Integrity Analysis of Flywheel of Reactor Coolant Pump in Nuclear Power Plant
Available to Purchase
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
Proceedings Papers
Stress Analysis of Three-Layer SiC Cladding for PWRs
Available to Purchase
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
Proceedings Papers
In-Service Inspection Technology Research on CANOPY Seal Weld of Control Rod Drive Mechanism in PWR
Available to Purchase
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
Proceedings Papers
The Surge Line Stress Analysis Model Setup With the Consideration of Thermal Stratification
Available to Purchase
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
Proceedings Papers
Materials and Stress Analysis of Fuel-Channel of a Generic 1200-MW el Pressure-Channel Reactor With Nuclear Steam Reheat
Available to Purchase
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
Proceedings Papers
Stress Analysis of the Canned Nuclear Coolant Pump Based on FSI
Available to Purchase
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
Proceedings Papers
End-to-End Technology of Modeling a Melt-Structure Interaction During IVMR in VVER With HEFEST-URAN Toolkit
Available to Purchase
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
Proceedings Papers
The Reliability Prediction of HTR’s Graphite Component in Various Temperature and Neutron Dose Levels
Available to Purchase
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
Proceedings Papers
The Measurement of the High Temperature Sodium Pipe in CEFR
Available to Purchase
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
Proceedings Papers
Stress Analysis and Assess for Nuclear Pipes of Class 1 Based on PIPESTRESS
Available to Purchase
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
Proceedings Papers
CFD Analysis of Thermal Stratification Phenomena in the RNS Suction Line of a Gen-III Nuclear Power Plant
Available to Purchase
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
Proceedings Papers
Analysis of Dynamic Effects Associated With Postulated Breaks of Piping
Available to Purchase
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
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