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Proceedings Papers

The Effects of Compressibility and Piping Geometry on Steamhammer Loads

Frederick J. Moody, Robert Stakenborghs
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T01A001, July 22–26, 2018
Paper No: ICONE26-81003
https://doi.org/10.1115/ICONE26-81003
View Paper titled, The Effects of Compressibility and Piping Geometry on Steamhammer Loads
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Topics: Compressibility, Geometry, Pipes, Stress, Flow (Dynamics), Valves, Turbines, ASME Standards, Fluids, Nuclear power stations
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
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

A Flow-Induced Vibration Study on the Multiple Rectangular Tubes Bundles for Steam Generator Outlet Pipes of HTR-PM

Song Yu, Zhou Qin, Zhao Jiaqing, Zhang Yiyang, Wu Xinxin
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A018, July 22–26, 2018
Paper No: ICONE26-81229
https://doi.org/10.1115/ICONE26-81229
View Paper titled, A Flow-Induced Vibration Study on the Multiple Rectangular Tubes Bundles for Steam Generator Outlet Pipes of HTR-PM
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Topics: Boilers, Flow-induced vibrations, Pipes, Cylinders, Vibration, High temperature, ASME Standards, Circular cylinders, Collisions (Physics), Damage
Proceedings Papers

Research on Simplified Method of Transients Combining and Loading in Fatigue Crack Growth Analysis of Carbon Steel Nuclear Piping

Zhenshun Liu, Hongdong Zhen
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A019, July 22–26, 2018
Paper No: ICONE26-81640
https://doi.org/10.1115/ICONE26-81640
View Paper titled, Research on Simplified Method of Transients Combining and Loading in Fatigue Crack Growth Analysis of Carbon Steel Nuclear Piping
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Topics: Carbon steel, Fatigue cracks, Pipes, Transients (Dynamics), Fracture (Materials), Stress, ASME Standards, Fatigue
Proceedings Papers

Numerical Research on Shock Resistance Safety Analysis of Ship Power Plant Valve

Jun Wu, Fan Bai, Yong Liu, Xingsheng Lao, Chunhui Dai
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A032, July 22–26, 2018
Paper No: ICONE26-82137
https://doi.org/10.1115/ICONE26-82137
View Paper titled, Numerical Research on Shock Resistance Safety Analysis of Ship Power Plant Valve
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Topics: Power stations, Safety, Ships, Shock (Mechanics), Valves, Stress, Modal analysis, Stress concentration, ASME Standards, Emission spectroscopy
Proceedings Papers

Review on Mechanical Design of Printed Circuit Heat Exchangers

Xiaoqin Zhang, Shanbin Shi, Richard N. Christensen, Xiaodong Sun
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A042, July 2–6, 2017
Paper No: ICONE25-67284
https://doi.org/10.1115/ICONE25-67284
View Paper titled, Review on Mechanical Design of Printed Circuit Heat Exchangers
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Topics: Circuits, Design engineering, Heat exchangers, Flow (Dynamics), Computer simulation, ASME Standards, Diffusion (Physics), Plates (structures), Strength (Materials), Airfoils
Proceedings Papers

Nonlinear Analysis Method Research of Multi-Bolt Connection Structure of Primary Equipment Support

Jianrong Zou, Shaochong Zhou
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A069, July 2–6, 2017
Paper No: ICONE25-66875
https://doi.org/10.1115/ICONE25-66875
View Paper titled, Nonlinear Analysis Method Research of Multi-Bolt Connection Structure of Primary Equipment Support
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Topics: ASME Standards, Boilers, Computational methods, Design, Engineering design, Finite element methods, Flange connections, Flanges, Girders, Junctions
Proceedings Papers

Nonlinear Finite Element Analysis of Class 1 Pressure Vessels

Mingya Chen, Weiwei Yu, Jinhua Shi, Feng Lu
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T07A004, July 2–6, 2017
Paper No: ICONE25-66910
https://doi.org/10.1115/ICONE25-66910
View Paper titled, Nonlinear Finite Element Analysis of Class 1 Pressure Vessels
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Topics: Finite element analysis, Pressure vessels, Stress, Design, Nozzles, Elastic analysis, Failure, Pipes, Reactor vessels, ASME Standards
Proceedings Papers

Machine GTAW Ambient Temperature Temper Bead Technique for Ni-Based Weld Overlay Repairs of Nuclear Components: Assessment of Hydrogen Cracking by Implant Test

Marcello Consonni, Claire Verdon
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, V001T01A031, July 2–6, 2017
Paper No: ICONE25-67160
https://doi.org/10.1115/ICONE25-67160
View Paper titled, Machine GTAW Ambient Temperature Temper Bead Technique for Ni-Based Weld Overlay Repairs of Nuclear Components: Assessment of Hydrogen Cracking by Implant Test
Open the PDF for Machine GTAW Ambient Temperature Temper Bead Technique for Ni-Based Weld Overlay Repairs of Nuclear Components: Assessment of Hydrogen Cracking by Implant Test in another window
Topics: Gas tungsten arc welding, Hydrogen embrittlement, Machinery, Maintenance, Overlays (Materials engineering), Temperature, Heating, Welding, Cracking (Materials), Fracture (Process)
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
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

Nuclear Air Cleaning Codes and Standards Development and Use in the United States

Ronald R. Bellamy
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T08A002, June 26–30, 2016
Paper No: ICONE24-60119
https://doi.org/10.1115/ICONE24-60119
View Paper titled, Nuclear Air Cleaning Codes and Standards Development and Use in the United States
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Topics: Engineering standards, Nuclear power stations, Safety, Testing, Accidents, Activated carbon, ASME Standards, ASTM International, Boiling water reactors, Construction
Proceedings Papers

A Study of Axial Compression in the ASME B&PV Code for Pipe Supports and Restraints

Phillip E. Wiseman, Zara Z. Hoch
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, V001T03A033, June 26–30, 2016
Paper No: ICONE24-61101
https://doi.org/10.1115/ICONE24-61101
View Paper titled, A Study of Axial Compression in the ASME B&PV Code for Pipe Supports and Restraints
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Topics: Compression, Pipes, Stress, ASME Boiler and Pressure Vessel Code, Buckling, Design, ASME Standards, Elastic analysis, Mechanical engineers, Stability
Proceedings Papers

3D Linear Bifurcation Analysis of Steel Containment Vessel

Jay Schmidt, Bernd Laskewitz
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, V001T03A018, June 26–30, 2016
Paper No: ICONE24-60673
https://doi.org/10.1115/ICONE24-60673
View Paper titled, 3D Linear Bifurcation Analysis of Steel Containment Vessel
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Topics: Bifurcation, Containment vessels, Steel, Shells, Stability, Buckling, Containment, Stress, ASME Boiler and Pressure Vessel Code, ASME Standards
Proceedings Papers

Microstructure and Mechanical Properties of 9Cr1Mo Steel-12Cr2Si Steel Bimetallic Billet Produced by Centrifugal Casting

Gidong Kim, Hong Ki Kim, Woosung Kim, Namkyu Kim, Sanghoon Lee, Sangwoo Song, Youngho Son
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A029, July 7–11, 2014
Paper No: ICONE22-31076
https://doi.org/10.1115/ICONE22-31076
View Paper titled, Microstructure and Mechanical Properties of 9Cr1Mo Steel-12Cr2Si Steel Bimetallic Billet Produced by Centrifugal Casting
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Topics: Casting, Mechanical properties, Steel, Corrosion resistance, High temperature, ASME Standards, Coolants, Fast neutron reactors, Ferrites (Magnetic materials), Heat treating (Metalworking)
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
https://doi.org/10.1115/ICONE22-30696
View Paper titled, Japanese Codes and Standards for Dual Purpose Metal Casks for Spent Nuclear Fuel
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Topics: Engineering standards, Metals, Spent nuclear fuels, Storage, Stress, Containment vessels, Japan Society of Mechanical Engineers, Safety, Design, Nuclear power stations
Proceedings Papers

Comparison of ASME Code NB-3200 and NB-3600-Based Environmental Fatigue Calculations for Piping Components

Kyeongjin Yang, Daesu Kim, Dongjae Lee, Joonho Lee, Sangbae Lee, Inyeung Kim
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, V001T07A001, July 7–11, 2014
Paper No: ICONE22-30166
https://doi.org/10.1115/ICONE22-30166
View Paper titled, Comparison of ASME Code NB-3200 and NB-3600-Based Environmental Fatigue Calculations for Piping Components
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Topics: ASME Standards, Fatigue, Pipes, Stress, Light water reactors, Accounting, Coolants, Design, Nuclear power stations, Piping design
Proceedings Papers

Concept of Standard System Based on China Current Nuclear Power Construction

Yuelan Yan
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, V001T07A003, July 7–11, 2014
Paper No: ICONE22-30530
https://doi.org/10.1115/ICONE22-30530
View Paper titled, Concept of Standard System Based on China Current Nuclear Power Construction
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Topics: China, Nuclear construction, Nuclear power, Construction, Nuclear power stations, Absorption, ASME Standards, Building codes, Design
Proceedings Papers

Seismic Response Spectrum Analysis on Advanced PWR Coolant System

Rong Duan, Lili Tong, Xuewu Cao
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A033, July 29–August 2, 2013
Paper No: ICONE21-15825
https://doi.org/10.1115/ICONE21-15825
View Paper titled, Seismic Response Spectrum Analysis on Advanced PWR Coolant System
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Topics: Coolants, Emission spectroscopy, Pressurized water reactors, Spectroscopy, Stress, Earthquakes, Boilers, Design, Pressure, Pumps
Proceedings Papers

A Study of Rules of Material Groupings in ASME IX QW-420 by Decision Tree Method

Lifeng Guo, Yaochun Zhang, Libo Shi, An Dong
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T07A004, July 29–August 2, 2013
Paper No: ICONE21-15291
https://doi.org/10.1115/ICONE21-15291
View Paper titled, A Study of Rules of Material Groupings in ASME IX QW-420 by Decision Tree Method
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Topics: ASME Standards, Base metals, Heat treating (Metalworking), Mechanical properties, Strategic materials, Welding, Welding operators
Proceedings Papers

Proposed Improvements of the ASME B&PV Code and Future Directions of CIWG

Jinquan Yan, Yinbiao He, Gang Li, Hao Yu
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T07A005, July 29–August 2, 2013
Paper No: ICONE21-15404
https://doi.org/10.1115/ICONE21-15404
View Paper titled, Proposed Improvements of the ASME B&PV Code and Future Directions of CIWG
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Topics: Acceptance criteria, ASME Standards, China, Construction, Design, Fatigue, Hydrostatic testing, Nuclear industry, Nuclear power stations, Power stations