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Proceedings Papers

Analytical Determination of Stress Indices and Stress Intensification Factor for an Extruded Nozzle of Super Pipe

Lv Feng, Zhou Gengyu, Qian Haiyang
Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A024, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-85144
https://doi.org/10.1115/PVP2018-85144
View Paper titled, Analytical Determination of Stress Indices and Stress Intensification Factor for an Extruded Nozzle of Super Pipe
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Topics: Nozzles, Pipes, Stress, ASME Standards, Finite element analysis, ASME Boiler and Pressure Vessel Code, Extruding, Finite element methods, Finite element model, Nuclear power stations
Proceedings Papers

Numerical Calculation of Fatigue Crack Growth for the Structures of Elbow and Tee Pipe Based on RCC-MR A16 Code

Peng Tang, Jiacheng Luo, Pengzhou Li, Lei Sun, Juan Luo
Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A056, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-85061
https://doi.org/10.1115/PVP2018-85061
View Paper titled, Numerical Calculation of Fatigue Crack Growth for the Structures of Elbow and Tee Pipe Based on RCC-MR A16 Code
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Topics: Fatigue cracks, Pipes, Pipeline systems, Stress, Coolants, Crack propagation, Fatigue, Flow-induced vibrations, Fracture (Materials), High pressure (Physics)
Proceedings Papers

Margins Assessment of Pressure-Temperature Limit Curves for a RPV

Lv Feng, Zhou Gengyu, Qian Haiyang
Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A025, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-85145
https://doi.org/10.1115/PVP2018-85145
View Paper titled, Margins Assessment of Pressure-Temperature Limit Curves for a RPV
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Topics: Pressure, Temperature, Nuclear power stations, Brittle fracture, Embrittlement, Fracture toughness, Heat, Irradiation (Radiation exposure), Phase transition temperature, Reactor vessels
Proceedings Papers

Advanced Assessment of Ductile Fracture Behaviour in Dissimilar Metal Welds Using X-Ray Tomography

W. J. Brayshaw, A. Cooper, A. H. Sherry, P. James
Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A042, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84014
https://doi.org/10.1115/PVP2018-84014
View Paper titled, Advanced Assessment of Ductile Fracture Behaviour in Dissimilar Metal Welds Using X-Ray Tomography
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Topics: Ductile fracture, Metals, Welded joints, X-rays, Fracture (Materials), Alloys, Damage, Fracture toughness, Fillers (Materials), Finite element analysis
Proceedings Papers

Derivation of Transverse Tensile Properties of Alloy 690 Steam Generator Tubes Using Ring-Tensile Specimen and Finite Element Analysis

Jongmin Kim, Minchul Kim
Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A020, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84828
https://doi.org/10.1115/PVP2018-84828
View Paper titled, Derivation of Transverse Tensile Properties of Alloy 690 Steam Generator Tubes Using Ring-Tensile Specimen and Finite Element Analysis
Open the PDF for Derivation of Transverse Tensile Properties of Alloy 690 Steam Generator Tubes Using Ring-Tensile Specimen and Finite Element Analysis in another window
Topics: Alloys, Boilers, Finite element analysis, Tensile strength, Displacement, Optimization, Pressurized water reactors, Stress, Accidents, Bending (Stress)
Proceedings Papers

Investigation of the Fatigue Behavior of Austenitic Stainless Steels and Their Welds for Reactor Internals Under Combined Low Cycle (LCF), High Cycle (HCF) and Very High Cycle (VHCF) Operational Loading Conditions

Xaver Schuler, Tim Schopf, Tilmann Beck, Marek Smaga, Tobias Daniel, Jürgen Rudolph, Birgit Buchholz
Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A060, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-85028
https://doi.org/10.1115/PVP2018-85028
View Paper titled, Investigation of the Fatigue Behavior of Austenitic Stainless Steels and Their Welds for Reactor Internals Under Combined Low Cycle (LCF), High Cycle (HCF) and Very High Cycle (VHCF) Operational Loading Conditions
Open the PDF for Investigation of the Fatigue Behavior of Austenitic Stainless Steels and Their Welds for Reactor Internals Under Combined Low Cycle (LCF), High Cycle (HCF) and Very High Cycle (VHCF) Operational Loading Conditions in another window
Topics: Cycles, Fatigue, High cycle fatigue, Stainless steel, Welded joints, Stress, Design, Damage, Deformation, Endurance limit
Proceedings Papers

A Study on the Pressure-Temperature Limit Curve Under High Cooling Rate for the Reactor Using Finite Element Method

Ye-Rin Choi, Min-Kyu Kim, Jae-Hee Kim, Tae-Young Ryu, Jun-Seog Yang, Moon Ki Kim, Jae-Boong Choi
Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A021, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84850
https://doi.org/10.1115/PVP2018-84850
View Paper titled, A Study on the Pressure-Temperature Limit Curve Under High Cooling Rate for the Reactor Using Finite Element Method
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Topics: Cooling, Finite element methods, Pressure, Temperature, ASME Standards, Nuclear power stations, Accidents, Finite element analysis, Safety, Thermal shock
Proceedings Papers

Two- and Three-Dimensional Weld Residual Stress Analysis of a Weld Overlay Mockup of a VVER Feedwater Nozzle Dissimilar Metal Weld

Francis H. Ku, Steven L. McCracken
Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A082, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84981
https://doi.org/10.1115/PVP2018-84981
View Paper titled, Two- and Three-Dimensional Weld Residual Stress Analysis of a Weld Overlay Mockup of a VVER Feedwater Nozzle Dissimilar Metal Weld
Open the PDF for Two- and Three-Dimensional Weld Residual Stress Analysis of a Weld Overlay Mockup of a VVER Feedwater Nozzle Dissimilar Metal Weld in another window
Topics: Feedwater, Metals, Nozzles, Overlays (Materials engineering), Stress analysis (Engineering), Pressurized water reactors, Design, Water, Emergencies, Finite element analysis
Proceedings Papers

Proposal of the Local Failure Evaluation Method With Stress Parameters

Takashi Sakaguchi, Mizuki Yoshida, Takuya Sato, Naoto Kasahara
Proc. ASME. PVP2018, Volume 3A: Design and Analysis, V03AT03A046, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84222
https://doi.org/10.1115/PVP2018-84222
View Paper titled, Proposal of the Local Failure Evaluation Method With Stress Parameters
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Topics: Evaluation methods, Failure, Stress, Fracture (Materials), Fracture (Process), Hydrostatics, Creep, Failure mechanisms, Nuclear power stations, Stress-strain curves
Proceedings Papers

An Introduction to the New ASME Standards on Nonmetallic Pressure Piping Systems

Charles L. Henley, Jeffrey D. Eisenman
Proc. ASME. PVP2018, Volume 3A: Design and Analysis, V03AT03A009, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84458
https://doi.org/10.1115/PVP2018-84458
View Paper titled, An Introduction to the New ASME Standards on Nonmetallic Pressure Piping Systems
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Topics: ASME Standards, Pressure pipes, Pipes, Nonmetallic materials, Design, Piping systems, Glass fibers, Manufacturing, Nuclear power stations, Resins
Proceedings Papers

Effect of 3-D Initial Imperfections on the Deformation Behaviors of Head Plates Subjected to Convex Side Pressure

Hiroki Yada, Masanori Ando, Kazuyuki Tsukimori, Masakazu Ichimiya, Yoshinari Anoda
Proc. ASME. PVP2018, Volume 3A: Design and Analysis, V03AT03A049, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84533
https://doi.org/10.1115/PVP2018-84533
View Paper titled, Effect of 3-D Initial Imperfections on the Deformation Behaviors of Head Plates Subjected to Convex Side Pressure
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Topics: Deformation, Plates (structures), Pressure, Finite element analysis, Buckling, Containment vessels, Design, Dimensions, Evaluation methods, External pressure
Proceedings Papers

Evaluation of Deformation and Fracture Behaviors of Nuclear Components Using a Simulated Specimen Under Excessive Seismic Loads

Jin Weon Kim, Ik Hyun Song, Hyeong Do Kweon, Jong Sung Kim, Yun Jae Kim
Proc. ASME. PVP2018, Volume 3A: Design and Analysis, V03AT03A050, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84576
https://doi.org/10.1115/PVP2018-84576
View Paper titled, Evaluation of Deformation and Fracture Behaviors of Nuclear Components Using a Simulated Specimen Under Excessive Seismic Loads
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Topics: Deformation, Fracture (Materials), Stress, Design, Displacement, Nuclear power stations, Temperature, Alloys, Cycles, Earthquakes
Proceedings Papers

Numerical Simulation on Flow Induced Vibration and Fretting Wear of a Steam Generator

Wei Tan, Kai Guo, Xiantao Fan, Yipeng Wang, Guorui Zhu, Liyan Liu
Proc. ASME. PVP2018, Volume 4: Fluid-Structure Interaction, V004T04A003, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84347
https://doi.org/10.1115/PVP2018-84347
View Paper titled, Numerical Simulation on Flow Induced Vibration and Fretting Wear of a Steam Generator
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Topics: Boilers, Computer simulation, Flow-induced vibrations, Wear, Fluids, Modeling, Porous materials, Design, Dynamic analysis, Corrosion
Proceedings Papers

Long-Term Operation of BWR RPV and its Internals

Otso Cronvall
Proc. ASME. PVP2018, Volume 7: Operations, Applications, and Components, V007T07A016, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84541
https://doi.org/10.1115/PVP2018-84541
View Paper titled, Long-Term Operation of BWR RPV and its Internals
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Topics: Boiling water reactors, Irradiation (Radiation exposure), Nuclear power stations, Stress, Brittleness, Embrittlement, Fatigue, Reactor vessels, Stress corrosion cracking, Temperature distribution
Proceedings Papers

New Generation of Monitoring Systems: From Measurement to Numerical Simulation

Benoît Jouan, Benedikt Heinz, Oana Zenaida Pascan
Proc. ASME. PVP2018, Volume 7: Operations, Applications, and Components, V007T07A005, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84598
https://doi.org/10.1115/PVP2018-84598
View Paper titled, New Generation of Monitoring Systems: From Measurement to Numerical Simulation
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Topics: Computer simulation, Monitoring systems, Finite element model, Nuclear power stations, Thermomechanics, Computation, Data acquisition systems, Heat exchangers, Temperature
Proceedings Papers

Qualification of Motor Actuated Valve Assemblies for Safety Related Nuclear Applications: Lessons Learned

Ronald Farrell, L. Ike Ezekoye
Proc. ASME. PVP2018, Volume 7: Operations, Applications, and Components, V007T07A025, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-85040
https://doi.org/10.1115/PVP2018-85040
View Paper titled, Qualification of Motor Actuated Valve Assemblies for Safety Related Nuclear Applications: Lessons Learned
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Topics: Engines, Motors, Safety, Valves, Electrical components, Nuclear power stations, Actuators, Electric motors, Manufacturing, Testing
Proceedings Papers

Comparison of Thermal Test Using Slice Model and Half-Scale Model of Shipping Package

Kyoung-Sik Bang, Seung-Hwan Yu, Ju-Chan Lee, Woo-Seok Choi
Proc. ASME. PVP2018, Volume 7: Operations, Applications, and Components, V007T07A034, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84260
https://doi.org/10.1115/PVP2018-84260
View Paper titled, Comparison of Thermal Test Using Slice Model and Half-Scale Model of Shipping Package
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Topics: Combustion, Concretes, Flames, Neutrons, Nuclear power stations, Safety, Security, Size reduction (Materials), Temperature
Proceedings Papers

Finite-Element Analysis of Crack Growth in Austenitic Stainless Steel Under Equibiaxial Loading

H. Dhahri, C. Gourdin, H. Maitournam
Proc. ASME. PVP2018, Volume 5: High-Pressure Technology; ASME Nondestructive Evaluation, Diagnosis and Prognosis Division (NDPD); Rudy Scavuzzo Student Paper Symposium and 26th Annual Student Paper Competition, V005T10A018, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84156
https://doi.org/10.1115/PVP2018-84156
View Paper titled, Finite-Element Analysis of Crack Growth in Austenitic Stainless Steel Under Equibiaxial Loading
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Topics: Finite element analysis, Fracture (Materials), Stainless steel, Pressurized water reactors, Fatigue, Stress, Fatigue life, Fatigue testing, Collaboration, Computer simulation
Proceedings Papers

An Improved Phased Array Ultrasonic Testing Technique for Thick-Wall Polyethylene Pipe Used in Nuclear Power Plant

Yinkang Qin, Jianfeng Shi, Jinyang Zheng
Proc. ASME. PVP2018, Volume 5: High-Pressure Technology; ASME Nondestructive Evaluation, Diagnosis and Prognosis Division (NDPD); Rudy Scavuzzo Student Paper Symposium and 26th Annual Student Paper Competition, V005T10A009, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84452
https://doi.org/10.1115/PVP2018-84452
View Paper titled, An Improved Phased Array Ultrasonic Testing Technique for Thick-Wall Polyethylene Pipe Used in Nuclear Power Plant
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Topics: Nuclear power stations, Polyethylene pipes, Ultrasonic testing, Delays, Acoustics, Computer simulation, Density, Errors, Flight, Imaging
Proceedings Papers

Investigation of Blast Wave Effects on Containment Wall and Steam Generator

Tae Jin Kim, Yoon-Suk Chang
Proc. ASME. PVP2018, Volume 5: High-Pressure Technology; ASME Nondestructive Evaluation, Diagnosis and Prognosis Division (NDPD); Rudy Scavuzzo Student Paper Symposium and 26th Annual Student Paper Competition, V005T10A005, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84325
https://doi.org/10.1115/PVP2018-84325
View Paper titled, Investigation of Blast Wave Effects on Containment Wall and Steam Generator
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Topics: Boilers, Containment, Waves, Damage, Failure, Finite element analysis, Fluids, High temperature, Nuclear power stations, Pipes