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Proceedings Papers

Effect of Coolant Water Temperature of ECCS on Failure Probability of RPV

Jinya Katsuyama, Koichi Masaki, Kai Lu, Tadashi Watanabe, Yinsheng Li

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A059, July 14–19, 2019

Paper No: PVP2019-93967

DOI: https://doi.org/10.1115/PVP2019-93967

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Topics: Coolants, Emergency core cooling systems, Failure, Fracture mechanics, Probability, Thermal shock, Water temperature, Temperature, Pressure, Pressurized water reactors

Proceedings Papers

Thermo-Mechanical Loading of Full-Scale Welded Piping Components in High Temperature Water Environment

Matthias C. Kammerer, Xaver Schuler, Stefan Weihe, Michael Seidenfuß, Mi Zhou, Eckart Laurien, Rudi Kulenovic

Proc. ASME. PVP2017, Volume 4: Fluid-Structure Interaction, V004T04A007, July 16–20, 2017

Paper No: PVP2017-65606

DOI: https://doi.org/10.1115/PVP2017-65606

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Topics: High temperature, Pipes, Thermomechanics, Water, Fatigue life, Fatigue, Fatigue testing, Steel, Temperature, Testing

Proceedings Papers

Traditional Versus New Technology Boiler Drum Water Level Instruments

Zhelin Liu, John Michael Harris, Jichuan Liu, Dong Han, Lei Liu

Proc. ASME. PVP2016, Volume 7: Operations, Applications and Components, V007T07A006, July 17–21, 2016

Paper No: PVP2016-63203

DOI: https://doi.org/10.1115/PVP2016-63203

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Topics: Boilers, Instrumentation, Water, Temperature, Errors, Density, Design, Steam, Control systems, Electrical conductivity

Proceedings Papers

Fatigue of Stainless Steel in Simulated Operational Conditions: Effects of PWR Water, Temperature and Holds

Jussi Solin, Sven Reese, H. Ertugrul Karabaki, Wolfgang Mayinger

Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A027, July 20–24, 2014

Paper No: PVP2014-28465

DOI: https://doi.org/10.1115/PVP2014-28465

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Topics: Fatigue, Pressurized water reactors, Stainless steel, Water temperature, Water, Design, Transients (Dynamics), Nuclear power stations, Pipes, Temperature

Proceedings Papers

Prediction of the Inner Temperatures in a Duct Based on Outer Thermocouples Measurements

Stéphane Gervais, Alexandre Girard

Proc. ASME. PVP2013, Volume 3: Design and Analysis, V003T03A032, July 14–18, 2013

Paper No: PVP2013-97048

DOI: https://doi.org/10.1115/PVP2013-97048

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Topics: Ducts, Temperature, Thermocouples, Computation, Fluids, Nuclear power stations, Algorithms, Approximation, Fatigue, Fatigue damage

Proceedings Papers

Startup and Shutdown Steam Generator Separator Piping Forces for a Coal-Fired Supercritical Power Plant

Rajgopal Vijaykumar, Julie M. Jarvis, Allen T. Vieira, James Humphrey, Dong Zheng

Proc. ASME. PVP2012, Volume 3: Design and Analysis, 701-707, July 15–19, 2012

Paper No: PVP2012-78798

DOI: https://doi.org/10.1115/PVP2012-78798

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Topics: Boilers, Coal, Pipes, Power stations, Valves, Stress, Transients (Dynamics), Condensed matter, Control systems, Boundary-value problems

Proceedings Papers

Thermal Fatigue Testing and Analysis of Stainless Steel Girth Butt Weld Piping

M. J. Zechmeister, R. D. Reinheimer, D. P. Jones, T. M. Damiani

Proc. ASME. PVP2011, Volume 1: Codes and Standards, 651-669, July 17–21, 2011

Paper No: PVP2011-58024

DOI: https://doi.org/10.1115/PVP2011-58024

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Topics: Fatigue testing, Pipes, Stainless steel, Design, Fatigue, Water, Welded joints, ASME Standards, Cycles, Fatigue cracks

Proceedings Papers

Underwater Testing of a Typical Ambient-Cure Epoxy Resin for Composite Repairs of Structural Piping and Vessels

Timothy S. Mally, Allison L. Johnston, Michael W. Keller, Roger H. Walker

Proc. ASME. PVP2011, Volume 7: Operations, Applications, and Components, 257-263, July 17–21, 2011

Paper No: PVP2011-57643

DOI: https://doi.org/10.1115/PVP2011-57643

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Topics: Composite materials, Epoxy resins, Maintenance, Pipes, Polymer composites, Testing, Vessels, Resins, Carbon fibers, Hardening (Curing)

Proceedings Papers

Study on Numerical Analysis of Temperature Fluctuations in a Mixing Piping

Chao-Jen Li, Yao-Long Tsai, Tai-Ping Tsai, Li-Hua Wang

Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 2, 319-328, July 18–22, 2010

Paper No: PVP2010-25103

DOI: https://doi.org/10.1115/PVP2010-25103

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Topics: Fluctuations (Physics), Numerical analysis, Pipes, Temperature, Turbulence, Water, Stress, Simulation, Simulation results, Wedges

Proceedings Papers

PTS Evaluation for Czech Nuclear Power Plants of WWER Type

Vladislav Pistora, Pavel Kral

Proc. ASME. PVP2009, Volume 7: Operations, Applications and Components, 217-224, July 26–30, 2009

Paper No: PVP2009-77405

DOI: https://doi.org/10.1115/PVP2009-77405

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Topics: Nuclear power stations, Finite element methods, Fracture (Materials), Stress, Emergency core cooling systems, Temperature, Brittleness, Circuits, Computation, Computers

Proceedings Papers

Thermal Fatigue Testing and Analysis of a Thick Perforated Ring

T. M. Damiani, J. E. Holliday, M. J. Zechmeister, R. D. Reinheimer, D. P. Jones

Proc. ASME. PVP2007, Volume 1: Codes and Standards, 313-331, July 22–26, 2007

Paper No: PVP2007-26364

DOI: https://doi.org/10.1115/PVP2007-26364

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Topics: Fatigue testing, Finite element analysis, Fatigue cracks, Algorithms, Cracking (Materials), Cycles, Fatigue, Fatigue life, Flow (Dynamics), Fluid dynamics

Proceedings Papers

Method to Evaluate Fatigue Life of Carbon Steel Under Simulated Synchronously Changing BWR Condition

Akihiko Hirano, Kazunari Uchida, Katsumi Sakaguchi

Proc. ASME. PVP2007, Volume 1: Codes and Standards, 219-229, July 22–26, 2007

Paper No: PVP2007-26422

DOI: https://doi.org/10.1115/PVP2007-26422

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Topics: Boiling water reactors, Carbon steel, Fatigue life, Flow (Dynamics), Oxygen, Temperature, Water, Fatigue, Fatigue testing, Structural elements (Construction)

Proceedings Papers

Ways for Extending the Reactor Pressure Vessel Lifetime

Milan Brumovsky

Proc. ASME. PVP2008, Volume 7: Operations, Applications and Components, 129-135, July 27–31, 2008

Paper No: PVP2008-61479

DOI: https://doi.org/10.1115/PVP2008-61479

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Topics: Reactor vessels, Vessels, Annealing, Design, Economics , Emergency core cooling systems, Fracture mechanics, Leakage, Manufacturing technology, Nuclear power stations

Proceedings Papers

Measurement of Pressure Drop in a Liquid Metal Reactor Fuel Assembly

Seok Ki Choi, Il Kon Choi, Kil Yong Lee, Ho Yun Nam, Jong Hyeun Choi, Hoon Ki Choi

Proc. ASME. PVP2002, Thermal Hydraulic Problems, Sloshing Phenomena, and Extreme Loads on Structures, 107-114, August 5–9, 2002

Paper No: PVP2002-1135

DOI: https://doi.org/10.1115/PVP2002-1135

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Topics: Liquid metals, Manufacturing, Nuclear fuels, Pressure drop, Fuels, Wire, Flow (Dynamics), Water, Water temperature

Proceedings Papers

Unit Cell Sparger Test Program and Preliminary Test Results for APR1400

Choon-Kyung Park, Seok Cho, Chul-Hwa Song, Se-Young Chun

Proc. ASME. PVP2002, Thermal Hydraulic Problems, Sloshing Phenomena, and Extreme Loads on Structures, 39-45, August 5–9, 2002

Paper No: PVP2002-1127

DOI: https://doi.org/10.1115/PVP2002-1127

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Topics: Bubbles, Flow (Dynamics), High pressure (Physics), Oscillations, Pressure, Pressurized water reactors, Steam, Stress, Temperature, Transients (Dynamics)

Proceedings Papers

The Modified Rate Approach Method to Evaluate Fatigue Life Under Synchronously Changing Temperature and Strain Rate in Elevated Temperature Water

Kazuya Tsutsumi, Makoto Higuchi, Kunihiro Iida, Yutaka Yamamoto

Proc. ASME. PVP2002, Pressure Vessel and Piping Codes and Standards, 99-107, August 5–9, 2002

Paper No: PVP2002-1227

DOI: https://doi.org/10.1115/PVP2002-1227

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Topics: Fatigue life, Temperature, Water, Fatigue, Fatigue damage, Steel, Transients (Dynamics), Water temperature

Proceedings Papers

Analysis of a Thermal Fatigue Test of a Stepped Pipe

D. P. Jones, J. E. Holliday, T. R. Leax, J. L. Gordon

Proc. ASME. PVP2004, Computer Technology and Applications, 67-77, July 25–29, 2004

Paper No: PVP2004-2748

DOI: https://doi.org/10.1115/PVP2004-2748

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Topics: Fatigue testing, Pipes, Cycles, Finite element analysis, Fracture (Materials), Fatigue, Stress, Fracture (Process), Oxygen, Stainless steel

Proceedings Papers

Unsteady Fluid/Solid Numerical Simulations to Evaluate Thermal Solicitations in PWR Nuclear Plant Mixing Zones

Thomas Pasutto, Christophe Pe´niguel, Marc Sakiz, Jean-Michel Ste´phan

Proc. ASME. PVP2005, Volume 4: Fluid Structure Interaction, 837-844, July 17–21, 2005

Paper No: PVP2005-71285

DOI: https://doi.org/10.1115/PVP2005-71285

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Topics: Computer simulation, Fluids, Nuclear power stations, Pressurized water reactors, Temperature, Junctions, Turbulence, Computational fluid dynamics, Fluctuations (Physics), Fluid dynamics

Proceedings Papers

Experimental Investigation for a Suitable Supercritical Reaction Container

Hironori Maehara, Shigeru Itoh, Yosuke Hemuki

Proc. ASME. PVP2006-ICPVT-11, Volume 4: Fluid Structure Interaction, Parts A and B, 331-334, July 23–27, 2006

Paper No: PVP2006-ICPVT-11-93478

DOI: https://doi.org/10.1115/PVP2006-ICPVT-11-93478

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Topics: Containers, Pressure, Temperature, Fluids, Supercritical fluids, Heating, Carbon dioxide, Corrosion resistance, Density, Energy consumption

Proceedings Papers

Modified Rate Approach Method to Evaluate Fatigue Life of Carbon Steel Under Simulated Synchronously Changing BWR Conditions

Akihiko Hirano, Katsumi Sakaguchi

Proc. ASME. PVP2006-ICPVT-11, Volume 3: Design and Analysis, 619-633, July 23–27, 2006

Paper No: PVP2006-ICPVT-11-94066

DOI: https://doi.org/10.1115/PVP2006-ICPVT-11-94066

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Topics: Boiling water reactors, Carbon steel, Fatigue life, Flow (Dynamics), Oxygen, Temperature, Water, Fatigue, Fatigue testing, Structural elements (Construction)

NARROW

Effect of Coolant Water Temperature of ECCS on Failure Probability of RPV

Thermo-Mechanical Loading of Full-Scale Welded Piping Components in High Temperature Water Environment

Traditional Versus New Technology Boiler Drum Water Level Instruments

Fatigue of Stainless Steel in Simulated Operational Conditions: Effects of PWR Water, Temperature and Holds

Prediction of the Inner Temperatures in a Duct Based on Outer Thermocouples Measurements

Startup and Shutdown Steam Generator Separator Piping Forces for a Coal-Fired Supercritical Power Plant

Thermal Fatigue Testing and Analysis of Stainless Steel Girth Butt Weld Piping

Underwater Testing of a Typical Ambient-Cure Epoxy Resin for Composite Repairs of Structural Piping and Vessels

Study on Numerical Analysis of Temperature Fluctuations in a Mixing Piping

PTS Evaluation for Czech Nuclear Power Plants of WWER Type

Thermal Fatigue Testing and Analysis of a Thick Perforated Ring

Method to Evaluate Fatigue Life of Carbon Steel Under Simulated Synchronously Changing BWR Condition

Ways for Extending the Reactor Pressure Vessel Lifetime

Measurement of Pressure Drop in a Liquid Metal Reactor Fuel Assembly

Unit Cell Sparger Test Program and Preliminary Test Results for APR1400

The Modified Rate Approach Method to Evaluate Fatigue Life Under Synchronously Changing Temperature and Strain Rate in Elevated Temperature Water

Analysis of a Thermal Fatigue Test of a Stepped Pipe

Unsteady Fluid/Solid Numerical Simulations to Evaluate Thermal Solicitations in PWR Nuclear Plant Mixing Zones

Experimental Investigation for a Suitable Supercritical Reaction Container

Modified Rate Approach Method to Evaluate Fatigue Life of Carbon Steel Under Simulated Synchronously Changing BWR Conditions

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