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Proceedings Papers

CCG of PE100 and Life Prediction of PE Pipe With Axial Semi-Elliptical Crack

Lei Zhang, Kaiming Lin, Yang Fu, Bingjun Gao

Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A035, July 14–19, 2019

Paper No: PVP2019-93556

DOI: https://doi.org/10.1115/PVP2019-93556

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Topics: Fracture (Materials), Polyethylene pipes, Creep, Pipes, Crack propagation, Displacement, Brittleness, Calibration, Corrosion resistance, Cracking (Materials)

Proceedings Papers

N-Bar Problems As Approximations to the Bree Problem

M. C. Messner, T.-L. Sham, Yanli Wang

Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A017, July 15–20, 2018

Paper No: PVP2018-84106

DOI: https://doi.org/10.1115/PVP2018-84106

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Topics: Approximation, ASME Boiler and Pressure Vessel Code, Cylinders, Design, Design methodology, Nuclear engineering, Pressure, Stress

Proceedings Papers

Numerical Study on the Creep Strain Characteristics for TMSR Reactor Coolant Piping Under Thermal Loading

Wei Gong, Xiaochun Zhang, Mingqiang Xie, Yuan Fu, Xiao Wang

Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A058, July 15–20, 2018

Paper No: PVP2018-84333

DOI: https://doi.org/10.1115/PVP2018-84333

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Topics: Creep, Nuclear reactor coolants, Pipes, Fatigue, Cycles, Damage, Stress, Computational methods, Design, Design methodology

Proceedings Papers

Numerical Simulation of Seismic Risk and Loss Propagation Effects in Process Plants: An Oil Refinery Case Study

Antonio C. Caputo, Alessandro Vigna

Proc. ASME. PVP2017, Volume 8: Seismic Engineering, V008T08A024, July 16–20, 2017

Paper No: PVP2017-65465

DOI: https://doi.org/10.1115/PVP2017-65465

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Topics: Computer simulation, Earthquake risk, Earthquakes, Accidents, Chain, Seismic hazard assessment, Engineering standards, Hazards, Industrial capacity, Nuclear engineering

Proceedings Papers

Further Evaluation of the Structural Integrity of the Chinese Qinshan 300-MWe Reactor Pressure Vessel Under Pressurized Thermal Shock Using the Master Curve Method

Yupeng Cao, Yinbiao He, Hui Hu, Hui Li

Proc. ASME. PVP2016, Volume 6A: Materials and Fabrication, V06AT06A039, July 17–21, 2016

Paper No: PVP2016-63799

DOI: https://doi.org/10.1115/PVP2016-63799

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Topics: Reactor vessels, Thermal shock, Fracture (Materials), Fracture mechanics, Design, Nuclear engineering, Nuclear power stations, Phase transition temperature, Transients (Dynamics)

Proceedings Papers

Full Scale Simulation-Based Study on Dynamic Response of BWR Fuel Assemblies Under Seismic Loading

Shinobu Yoshimura, Tomonori Yamada, Yuichi Koide, Shohei Onitsuka, Tadashi Iijima

Proc. ASME. PVP2015, Volume 8: Seismic Engineering, V008T08A048, July 19–23, 2015

Paper No: PVP2015-45334

DOI: https://doi.org/10.1115/PVP2015-45334

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Topics: Boiling water reactors, Dynamic response, Fuels, Simulation, Coolants, Finite element methods, Water, Acoustics, Computer simulation, Design

Proceedings Papers

Re-Evaluation of the Structural Integrity of the Chinese Qinshan 300-MWe Reactor Pressure Vessel Under Pressurized Thermal Shock Using the Master Curve Method

Yupeng Cao, Yinbiao He, Hu Hui, Hui Li, Fuzhen Xuan

Proc. ASME. PVP2015, Volume 6A: Materials and Fabrication, V06AT06A033, July 19–23, 2015

Paper No: PVP2015-45577

DOI: https://doi.org/10.1115/PVP2015-45577

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Topics: Reactor vessels, Thermal shock, Accidents, Coolants, Design, Fracture (Materials), Transients (Dynamics), Cladding systems (Building), Nuclear engineering, Nuclear power stations

Proceedings Papers

Rules for Temporary Repair Techniques in JSME Fitness-for-Service Code and Their Challenges

Koji Dozaki, Hiroyuki Kobayashi, Hiroyuki Adachi, Katsuhide Muraoka, Yusuke Kono

Proc. ASME. PVP2015, Volume 1B: Codes and Standards, V01BT01A060, July 19–23, 2015

Paper No: PVP2015-45903

DOI: https://doi.org/10.1115/PVP2015-45903

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Topics: Fitness-for-service, Japan Society of Mechanical Engineers, Maintenance, Design, Leakage, Nuclear power stations, Adhesion, Energy engineering, Flanges, Inspection

Proceedings Papers

Further Development of the Nonlocal Damage Model of Rousselier for the Transition Regime of Fracture Toughness and Different Stress States

Sarah Gehrlicher, Michael Seidenfuss, Xaver Schuler

Proc. ASME. PVP2014, Volume 3: Design and Analysis, V003T03A097, July 20–24, 2014

Paper No: PVP2014-28714

DOI: https://doi.org/10.1115/PVP2014-28714

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Topics: Damage, Fracture toughness, Stress, Fracture (Materials), Damage mechanics, Safety, Brittleness, Failure, Brittle fracture, Computation

Proceedings Papers

Updated Knowledge Implemented to the Revision of Environmental Fatigue Evaluation Method for Nuclear Power Plant in JSME Code

Makoto Higuchi, Takao Nakamura, Yasuaki Sugie

Proc. ASME. PVP2009, Volume 1: Codes and Standards, 123-132, July 26–30, 2009

Paper No: PVP2009-77077

DOI: https://doi.org/10.1115/PVP2009-77077

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Topics: Evaluation methods, Fatigue, JSME Standards, Nuclear power stations, Light water reactors, Nuclear power, Coolants, Electrohydrodynamics, Fatigue life, Safety

Proceedings Papers

Nonlinear Seismic Correlation Analysis of the JNES/NUPEC Large-Scale Piping System Tests

Jinsuo Nie, Giuliano DeGrassi, Charles H. Hofmayer, Syed A. Ali

Proc. ASME. PVP2008, Volume 8: Seismic Engineering, 275-287, July 27–31, 2008

Paper No: PVP2008-61881

DOI: https://doi.org/10.1115/PVP2008-61881

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Topics: Piping systems, Pipes, Analytical methods, Collaboration, Failure mechanisms, Finite element model, Nuclear engineering, Nuclear power, Nuclear power stations, Safety

Proceedings Papers

Inspection and Evaluation Guidelines for Light Water Reactor Core Internals in Japan

Kimihito Takeuchi, Naoto Iizuka, Masashi Kameyama, Haruo Fujimori, Yuichi Motora, Koji Koyama

Proc. ASME. PVP2002, Service Experience and Failure Assessment Applications, 47-53, August 5–9, 2002

Paper No: PVP2002-1174

DOI: https://doi.org/10.1115/PVP2002-1174

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Topics: Inspection, Light water reactors, Boiling water reactors, Cracking (Materials), Fracture (Process), Instrumentation, Jet pumps, Maintenance, Nuclear engineering, Nuclear power stations

Proceedings Papers

Seismic Proving Test of Heavy Component With Energy Absorbing Support: Proving Test Results

T. Iwatsubo, M. Konno, H. Abe, K. Kuroda, K. Tai, H. Sumiya

Proc. ASME. PVP2002, Seismic Engineering, Volume 1, 107-111, August 5–9, 2002

Paper No: PVP2002-1404

DOI: https://doi.org/10.1115/PVP2002-1404

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Topics: Boilers, Damage, Dampers, Design, Earthquakes, Economics , Engineering laboratories, Extruding, Generators, Nuclear engineering

Proceedings Papers

Guidelines on Environmental Fatigue Evaluation for LWR Component

Takao Nakamura, Itaru Saito, Yasuhide Asada

Proc. ASME. PVP2003, Pressure Vessel and Piping Codes and Standards, 161-171, July 20–24, 2003

Paper No: PVP2003-1780

DOI: https://doi.org/10.1115/PVP2003-1780

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Topics: Fatigue, Light water reactors, Public utilities, Fatigue life, Nuclear engineering

Proceedings Papers

Crack Shape Development of Two Interacting Surface Elliptical Cracks

S. K. Patel, B. Dattaguru, K. Ramachandra

Proc. ASME. PVP2003, Computer Technology and Applications, 243-251, July 20–24, 2003

Paper No: PVP2003-1909

DOI: https://doi.org/10.1115/PVP2003-1909

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Topics: Fracture (Materials), Shapes, Aerospace industry, Damage, Pipes, Degrees of freedom, Fatigue, Fatigue cracks, Fittings, Life extension

Proceedings Papers

Seismic Response Prediction of NUPEC’s Field Model Tests of NPP Structures With Adjacent Building Effect

J. Xu, C. Costantino, C. Hofmayer, S. Ali

Proc. ASME. PVP2004, Seismic Engineering, Volume 1, 1-11, July 25–29, 2004

Paper No: PVP2004-2898

DOI: https://doi.org/10.1115/PVP2004-2898

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Topics: Nuclear power stations, Seismic analysis, Soil, Structures, Computers, Earthquakes, Nuclear engineering, Turbines

Proceedings Papers

Seismic Analysis of a Nuclear Reactor With Fluid-Structure Interaction

Jean-Franc¸ois Sigrist, Daniel Broc, Christian Laine

Proc. ASME. PVP2005, Volume 4: Fluid Structure Interaction, 37-44, July 17–21, 2005

Paper No: PVP2005-71182

DOI: https://doi.org/10.1115/PVP2005-71182

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Topics: Fluid structure interaction, Nuclear reactors, Seismic analysis, Fluids, Computer simulation, Stiffness, Design, Engineering prototypes, Finite element analysis, Modal analysis

Proceedings Papers

Evaluation of Environmental Fatigue in PWR PLM Activities

Masanobu Iwasaki, Yasukazu Takada, Takao Nakamura

Proc. ASME. PVP2005, Volume 1: Codes and Standards, 183-191, July 17–21, 2005

Paper No: PVP2005-71509

DOI: https://doi.org/10.1115/PVP2005-71509

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Topics: Fatigue, Pressurized water reactors, Japan Society of Mechanical Engineers, Light water reactors, Maintenance, Nuclear engineering, Nuclear power stations, Public utilities

Proceedings Papers

Multiaxial Time-Dependent Cyclic Deformation of Stainless Steel at High Temperatures

Qing Gao, Zhi Shi, Guozheng Kang, Yujie Liu

Proc. ASME. PVP2006-ICPVT-11, Volume 6: Materials and Fabrication, 367-372, July 23–27, 2006

Paper No: PVP2006-ICPVT-11-93300

DOI: https://doi.org/10.1115/PVP2006-ICPVT-11-93300

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Topics: Deformation, High temperature, Stainless steel, Design, Nuclear engineering, Pipes

Proceedings Papers

JSME Codes on Environmental Fatigue Evaluation

Takao Nakamura, Makoto Higuchi, Takehiro Kusunoki, Yasuaki Sugie

Proc. ASME. PVP2006-ICPVT-11, Volume 1: Codes and Standards, 129-138, July 23–27, 2006

Paper No: PVP2006-ICPVT-11-93305

DOI: https://doi.org/10.1115/PVP2006-ICPVT-11-93305

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Topics: Fatigue, JSME Standards, Japan Society of Mechanical Engineers, Evaluation methods, Fatigue life, Light water reactors, Public utilities, Concretes, Natural resources, Nuclear engineering

NARROW

CCG of PE100 and Life Prediction of PE Pipe With Axial Semi-Elliptical Crack

N-Bar Problems As Approximations to the Bree Problem

Numerical Study on the Creep Strain Characteristics for TMSR Reactor Coolant Piping Under Thermal Loading

Numerical Simulation of Seismic Risk and Loss Propagation Effects in Process Plants: An Oil Refinery Case Study

Further Evaluation of the Structural Integrity of the Chinese Qinshan 300-MWe Reactor Pressure Vessel Under Pressurized Thermal Shock Using the Master Curve Method

Full Scale Simulation-Based Study on Dynamic Response of BWR Fuel Assemblies Under Seismic Loading

Re-Evaluation of the Structural Integrity of the Chinese Qinshan 300-MWe Reactor Pressure Vessel Under Pressurized Thermal Shock Using the Master Curve Method

Rules for Temporary Repair Techniques in JSME Fitness-for-Service Code and Their Challenges

Further Development of the Nonlocal Damage Model of Rousselier for the Transition Regime of Fracture Toughness and Different Stress States

Updated Knowledge Implemented to the Revision of Environmental Fatigue Evaluation Method for Nuclear Power Plant in JSME Code

Nonlinear Seismic Correlation Analysis of the JNES/NUPEC Large-Scale Piping System Tests

Inspection and Evaluation Guidelines for Light Water Reactor Core Internals in Japan

Seismic Proving Test of Heavy Component With Energy Absorbing Support: Proving Test Results

Guidelines on Environmental Fatigue Evaluation for LWR Component

Crack Shape Development of Two Interacting Surface Elliptical Cracks

Seismic Response Prediction of NUPEC’s Field Model Tests of NPP Structures With Adjacent Building Effect

Seismic Analysis of a Nuclear Reactor With Fluid-Structure Interaction

Evaluation of Environmental Fatigue in PWR PLM Activities

Multiaxial Time-Dependent Cyclic Deformation of Stainless Steel at High Temperatures

JSME Codes on Environmental Fatigue Evaluation

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