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Proceedings Papers

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

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Lei Zhang, Kaiming Lin, Yang Fu, Bingjun Gao
Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A035, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93556
https://doi.org/10.1115/PVP2019-93556
View Paper titled, CCG of PE100 and Life Prediction of PE Pipe With Axial Semi-Elliptical Crack
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Topics: Fracture (Materials), Polyethylene pipes, Creep, Pipes, Crack propagation, Displacement, Brittleness, Calibration, Corrosion resistance, Cracking (Materials)
Proceedings Papers

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

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Wei Gong, Xiaochun Zhang, Mingqiang Xie, Yuan Fu, Xiao Wang
Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A058, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84333
https://doi.org/10.1115/PVP2018-84333
View Paper titled, Numerical Study on the Creep Strain Characteristics for TMSR Reactor Coolant Piping Under Thermal Loading
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Topics: Creep, Nuclear reactor coolants, Pipes, Fatigue, Cycles, Damage, Stress, Computational methods, Design, Design methodology
Proceedings Papers

N-Bar Problems As Approximations to the Bree Problem

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M. C. Messner, T.-L. Sham, Yanli Wang
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A017, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84106
https://doi.org/10.1115/PVP2018-84106
View Paper titled, N-Bar Problems As Approximations to the Bree Problem
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Topics: Approximation, ASME Boiler and Pressure Vessel Code, Cylinders, Design, Design methodology, Nuclear engineering, Pressure, Stress
Proceedings Papers

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

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Antonio C. Caputo, Alessandro Vigna
Proc. ASME. PVP2017, Volume 8: Seismic Engineering, V008T08A024, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65465
https://doi.org/10.1115/PVP2017-65465
View Paper titled, Numerical Simulation of Seismic Risk and Loss Propagation Effects in Process Plants: An Oil Refinery Case Study
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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

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Yupeng Cao, Yinbiao He, Hui Hu, Hui Li
Proc. ASME. PVP2016, Volume 6A: Materials and Fabrication, V06AT06A039, July 17–21, 2016
Publisher: American Society of Mechanical Engineers
Paper No: PVP2016-63799
https://doi.org/10.1115/PVP2016-63799
View Paper titled, Further Evaluation of the Structural Integrity of the Chinese Qinshan 300-MWe Reactor Pressure Vessel Under Pressurized Thermal Shock Using the Master Curve Method
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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

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

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Koji Dozaki, Hiroyuki Kobayashi, Hiroyuki Adachi, Katsuhide Muraoka, Yusuke Kono
Proc. ASME. PVP2015, Volume 1B: Codes and Standards, V01BT01A060, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45903
https://doi.org/10.1115/PVP2015-45903
View Paper titled, Rules for Temporary Repair Techniques in JSME Fitness-for-Service Code and Their Challenges
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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

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

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Shinobu Yoshimura, Tomonori Yamada, Yuichi Koide, Shohei Onitsuka, Tadashi Iijima
Proc. ASME. PVP2015, Volume 8: Seismic Engineering, V008T08A048, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45334
https://doi.org/10.1115/PVP2015-45334
View Paper titled, Full Scale Simulation-Based Study on Dynamic Response of BWR Fuel Assemblies Under Seismic Loading
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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

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Yupeng Cao, Yinbiao He, Hu Hui, Hui Li, Fuzhen Xuan
Proc. ASME. PVP2015, Volume 6A: Materials and Fabrication, V06AT06A033, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45577
https://doi.org/10.1115/PVP2015-45577
View Paper titled, Re-Evaluation of the Structural Integrity of the Chinese Qinshan 300-MWe Reactor Pressure Vessel Under Pressurized Thermal Shock Using the Master Curve Method
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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

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

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Sarah Gehrlicher, Michael Seidenfuss, Xaver Schuler
Proc. ASME. PVP2014, Volume 3: Design and Analysis, V003T03A097, July 20–24, 2014
Publisher: American Society of Mechanical Engineers
Paper No: PVP2014-28714
https://doi.org/10.1115/PVP2014-28714
View Paper titled, Further Development of the Nonlocal Damage Model of Rousselier for the Transition Regime of Fracture Toughness and Different Stress States
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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

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Makoto Higuchi, Takao Nakamura, Yasuaki Sugie
Proc. ASME. PVP2009, Volume 1: Codes and Standards, 123-132, July 26–30, 2009
Publisher: American Society of Mechanical Engineers
Paper No: PVP2009-77077
https://doi.org/10.1115/PVP2009-77077
View Paper titled, Updated Knowledge Implemented to the Revision of Environmental Fatigue Evaluation Method for Nuclear Power Plant in JSME Code
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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

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Jinsuo Nie, Giuliano DeGrassi, Charles H. Hofmayer, Syed A. Ali
Proc. ASME. PVP2008, Volume 8: Seismic Engineering, 275-287, July 27–31, 2008
Publisher: American Society of Mechanical Engineers
Paper No: PVP2008-61881
https://doi.org/10.1115/PVP2008-61881
View Paper titled, Nonlinear Seismic Correlation Analysis of the JNES/NUPEC Large-Scale Piping System Tests
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2002-1174
https://doi.org/10.1115/PVP2002-1174
View Paper titled, Inspection and Evaluation Guidelines for Light Water Reactor Core Internals in Japan
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2002-1404
https://doi.org/10.1115/PVP2002-1404
View Paper titled, Seismic Proving Test of Heavy Component With Energy Absorbing Support: Proving Test Results
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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

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Takao Nakamura, Itaru Saito, Yasuhide Asada
Proc. ASME. PVP2003, Pressure Vessel and Piping Codes and Standards, 161-171, July 20–24, 2003
Publisher: American Society of Mechanical Engineers
Paper No: PVP2003-1780
https://doi.org/10.1115/PVP2003-1780
View Paper titled, Guidelines on Environmental Fatigue Evaluation for LWR Component
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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

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S. K. Patel, B. Dattaguru, K. Ramachandra
Proc. ASME. PVP2003, Computer Technology and Applications, 243-251, July 20–24, 2003
Publisher: American Society of Mechanical Engineers
Paper No: PVP2003-1909
https://doi.org/10.1115/PVP2003-1909
View Paper titled, Crack Shape Development of Two Interacting Surface Elliptical Cracks
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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

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J. Xu, C. Costantino, C. Hofmayer, S. Ali
Proc. ASME. PVP2004, Seismic Engineering, Volume 1, 1-11, July 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: PVP2004-2898
https://doi.org/10.1115/PVP2004-2898
View Paper titled, Seismic Response Prediction of NUPEC’s Field Model Tests of NPP Structures With Adjacent Building Effect
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Topics: Nuclear power stations, Seismic analysis, Soil, Structures, Computers, Earthquakes, Nuclear engineering, Turbines
Proceedings Papers

Evaluation of Environmental Fatigue in PWR PLM Activities

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Masanobu Iwasaki, Yasukazu Takada, Takao Nakamura
Proc. ASME. PVP2005, Volume 1: Codes and Standards, 183-191, July 17–21, 2005
Publisher: American Society of Mechanical Engineers
Paper No: PVP2005-71509
https://doi.org/10.1115/PVP2005-71509
View Paper titled, Evaluation of Environmental Fatigue in PWR PLM Activities
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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

Seismic Analysis of a Nuclear Reactor With Fluid-Structure Interaction

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Jean-Franc¸ois Sigrist, Daniel Broc, Christian Laine
Proc. ASME. PVP2005, Volume 4: Fluid Structure Interaction, 37-44, July 17–21, 2005
Publisher: American Society of Mechanical Engineers
Paper No: PVP2005-71182
https://doi.org/10.1115/PVP2005-71182
View Paper titled, Seismic Analysis of a Nuclear Reactor With Fluid-Structure Interaction
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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

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

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Qing Gao, Zhi Shi, Guozheng Kang, Yujie Liu
Proc. ASME. PVP2006-ICPVT-11, Volume 6: Materials and Fabrication, 367-372, July 23–27, 2006
Publisher: American Society of Mechanical Engineers
Paper No: PVP2006-ICPVT-11-93300
https://doi.org/10.1115/PVP2006-ICPVT-11-93300
View Paper titled, Multiaxial Time-Dependent Cyclic Deformation of Stainless Steel at High Temperatures
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Topics: Deformation, High temperature, Stainless steel, Design, Nuclear engineering, Pipes
Proceedings Papers

R&D and Its Application to NPPs on Aging Management and Lifetime Assessment

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Yikang Dou, Yinbiao He, Xuelian Xu, Yongcheng Xie
Proc. ASME. PVP2006-ICPVT-11, Volume 7: Operations, Applications, and Components, 49-55, July 23–27, 2006
Publisher: American Society of Mechanical Engineers
Paper No: PVP2006-ICPVT-11-93186
https://doi.org/10.1115/PVP2006-ICPVT-11-93186
View Paper titled, R&D and Its Application to NPPs on Aging Management and Lifetime Assessment
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Topics: Nuclear power stations, China, Design, Regulations, Nuclear engineering, Safety