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Proceedings Papers

Leak Rate Computation: Flow Resistance vs. Thermal-Hydraulic Aspect

Klaus Heckmann, Jürgen Sievers, Fabian Weyermann
Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A006, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84534
https://doi.org/10.1115/PVP2018-84534
View Paper titled, Leak Rate Computation: Flow Resistance vs. Thermal-Hydraulic Aspect
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Topics: Computation, Flow (Dynamics), Leakage, Fracture (Materials), Equilibrium (Physics), Modeling, Databases, Pressure, Analytical methods, Computer software
Proceedings Papers

Thermo-Mechanical Justification of the FA3 RPV Cover and Bottom Domes Under Normal and Upset, Emergency and Faulted Loading Situations

S. Chapuliot, M. Sportisse, J. Hardouin, S. Vidard
Proc. ASME. PVP2018, Volume 6A: Materials and Fabrication, V06AT06A072, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84553
https://doi.org/10.1115/PVP2018-84553
View Paper titled, Thermo-Mechanical Justification of the FA3 RPV Cover and Bottom Domes Under Normal and Upset, Emergency and Faulted Loading Situations
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Topics: Domes (Structural elements), Emergencies, Thermomechanics, Carbon, Thermal hydraulics
Proceedings Papers

A Thermomechanical PWR Test Facility to Investigate Thermal Shock Loading on a Small Scale Tubular Specimen

Peter Gill, Norman Platts, Chris Currie, Eleanor Grieveson
Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A027, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84923
https://doi.org/10.1115/PVP2018-84923
View Paper titled, A Thermomechanical PWR Test Facility to Investigate Thermal Shock Loading on a Small Scale Tubular Specimen
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Topics: Pressurized water reactors, Test facilities, Thermal shock, Thermomechanics, Geometry, Stress analysis (Engineering), Finite element analysis, Flow (Dynamics), Heat transfer coefficients, Temperature
Proceedings Papers

Fracture-Mechanics Analysis of the Reactor Pressure Vessel Beznau 1 Based on Thermal-Hydraulics Input Data From KWU-MIX and CFD Analyses

Tomas Nicak, Richard Trewin, Elisabeth Keim, Ingo Cremer, Sebastien Blasset, Heinz Hägeli
Proc. ASME. PVP2016, Volume 6A: Materials and Fabrication, V06AT06A065, July 17–21, 2016
Publisher: American Society of Mechanical Engineers
Paper No: PVP2016-63459
https://doi.org/10.1115/PVP2016-63459
View Paper titled, Fracture-Mechanics Analysis of the Reactor Pressure Vessel Beznau 1 Based on Thermal-Hydraulics Input Data From KWU-MIX and CFD Analyses
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Topics: Computational fluid dynamics, Fracture mechanics, Reactor vessels, Thermal hydraulics, Stress, Water, Brittleness, Failure, Plumes (Fluid dynamics), Thermal shock
Proceedings Papers

Loading Condition Evaluation for Structural Integrity Assessment of RPV due to PTS Event Based on Three-Dimensional Thermal-Hydraulics and Structural Analyses

Shumpei Uno, Jinya Katsuyama, Tadashi Watanabe, Yinsheng Li
Proc. ASME. PVP2016, Volume 1B: Codes and Standards, V01BT01A039, July 17–21, 2016
Publisher: American Society of Mechanical Engineers
Paper No: PVP2016-63443
https://doi.org/10.1115/PVP2016-63443
View Paper titled, Loading Condition Evaluation for Structural Integrity Assessment of RPV due to PTS Event Based on Three-Dimensional Thermal-Hydraulics and Structural Analyses
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Topics: Structural analysis, Thermal hydraulics, Coolants, Water, Heat transfer coefficients, Cladding systems (Building), Heat treating (Metalworking), Overlays (Materials engineering), Pressurized water reactors, Reactor vessels
Proceedings Papers

Prediction of Dynamic Break-Opening Area Under Beyond Design Basis Seismic Loading

M. Uddin, E. Kurth, F. W. Brust, G. M. Wilkowski, A. A. Betervide, O. Mazzantini, R. A. Fernandez
Proc. ASME. PVP2015, Volume 6A: Materials and Fabrication, V06AT06A078, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45156
https://doi.org/10.1115/PVP2015-45156
View Paper titled, Prediction of Dynamic Break-Opening Area Under Beyond Design Basis Seismic Loading
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Topics: Design, Fracture (Materials), Pipes, Rotation, Finite element analysis, Displacement, Accidents, Boiling water reactors, Computers, Coolants
Proceedings Papers

Study on Structural Integrity Assessment of Reactor Pressure Vessel Based on Three-Dimensional Thermal-Hydraulics and Structural Analyses

Jinya Katsuyama, Genshichiro Katsumata, Kunio Onizawa, Tadashi Watanabe, Yutaka Nishiyama
Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A097, July 20–24, 2014
Publisher: American Society of Mechanical Engineers
Paper No: PVP2014-28645
https://doi.org/10.1115/PVP2014-28645
View Paper titled, Study on Structural Integrity Assessment of Reactor Pressure Vessel Based on Three-Dimensional Thermal-Hydraulics and Structural Analyses
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Topics: Reactor vessels, Structural analysis, Thermal hydraulics, Coolants, Water, Crack propagation, Fracture (Materials), Heat transfer coefficients, Pressure vessels, Pressurized water reactors
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-97048
https://doi.org/10.1115/PVP2013-97048
View Paper titled, Prediction of the Inner Temperatures in a Duct Based on Outer Thermocouples Measurements
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Topics: Ducts, Temperature, Thermocouples, Computation, Fluids, Nuclear power stations, Algorithms, Approximation, Fatigue, Fatigue damage
Proceedings Papers

Measurement of Pressure Loss Throughout a Clogged Steam Generator Tube Support Plate in Single Phase Flow

Olivier Brunin, Geoffrey Deotto, Franck David, Joe¨l Pillet, Gilles Dague, Alexandre Nicoli
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 7, 65-72, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25606
https://doi.org/10.1115/PVP2010-25606
View Paper titled, Measurement of Pressure Loss Throughout a Clogged Steam Generator Tube Support Plate in Single Phase Flow
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Topics: Boilers, Flow (Dynamics), Pressure, Plates (structures), Two-phase flow, Refrigerants, Water, Computation, Computational methods, Heat
Proceedings Papers

Loads Applied to Clogged Steam Generators Internal Structures

Olivier Brunin, Geoffrey Deotto
Proc. ASME. PVP2009, Volume 7: Operations, Applications and Components, 181-190, July 26–30, 2009
Publisher: American Society of Mechanical Engineers
Paper No: PVP2009-77140
https://doi.org/10.1115/PVP2009-77140
View Paper titled, Loads Applied to Clogged Steam Generators Internal Structures
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Topics: Boilers, Stress, Flow (Dynamics), Cooling, Heat transfer, Mechanical behavior, Modeling, Oscillations, Risk, Safety
Proceedings Papers

Good Practice Handbook for PTS Evaluation (Result of the IAEA Co-Ordinated Project on PTS)

Vladislav Pistora, Milan Brumovsky, Nigel Taylor
Proc. ASME. PVP2009, Volume 3: Design and Analysis, 387-393, July 26–30, 2009
Publisher: American Society of Mechanical Engineers
Paper No: PVP2009-77396
https://doi.org/10.1115/PVP2009-77396
View Paper titled, Good Practice Handbook for PTS Evaluation (Result of the IAEA Co-Ordinated Project on PTS)
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Topics: Carbon reinforced plastics, Computation, Computational methods, Emergencies, Fracture (Materials), Nozzles, Reactor vessels, Stress, Temperature, Thermal hydraulics
Proceedings Papers

Materials Aging Degradation of Reactor Vessel Internals: Part I — Thermal Hydraulics Evaluation

Tama´s R. Liszkai, Norm S. Yee, Jim R. Smotrel, Anne Demma
Proc. ASME. PVP2008, Volume 4: Fluid-Structure Interaction, 303-312, July 27–31, 2008
Publisher: American Society of Mechanical Engineers
Paper No: PVP2008-61804
https://doi.org/10.1115/PVP2008-61804
View Paper titled, Materials Aging Degradation of Reactor Vessel Internals: Part I — Thermal Hydraulics Evaluation
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Topics: Reactor vessels, Thermal hydraulics, Physics, Computational fluid dynamics, Irradiation (Radiation exposure), Pressurized water reactors, Failure mechanisms, Inspection, Manufacturing, Radiation (Physics)
Proceedings Papers

Engineering Approach for the Reactor Pressure Vessel Integrity in PTS Conditions: Thermal Hydraulic and Fracture Mechanics Studies of a Safety Injection in a Three Loop Power Plant — French Benchmark With EDF and AREVA-NP Tools

A. Martin, A. Dahl, F. Lestang, S. Bellet, F. Beaud, Ph. Gilles, D. Guichard, Ph. Dolleans, S. Cornille, L. Maas
Proc. ASME. PVP2008, Volume 7: Operations, Applications and Components, 597-604, July 27–31, 2008
Publisher: American Society of Mechanical Engineers
Paper No: PVP2008-61717
https://doi.org/10.1115/PVP2008-61717
View Paper titled, Engineering Approach for the Reactor Pressure Vessel Integrity in PTS Conditions: Thermal Hydraulic and Fracture Mechanics Studies of a Safety Injection in a Three Loop Power Plant — French Benchmark With EDF and AREVA-NP Tools
Open the PDF for Engineering Approach for the Reactor Pressure Vessel Integrity in PTS Conditions: Thermal Hydraulic and Fracture Mechanics Studies of a Safety Injection in a Three Loop Power Plant — French Benchmark With EDF and AREVA-NP Tools in another window
Topics: Fracture mechanics, Power stations, Reactor vessels, Safety, Thermal hydraulics, Thermal shock
Proceedings Papers

CFD-Tool for Thermal-Hydraulics Pressurised Thermal Shock Analysis: Qualification of the Code_Saturne

A. Martin, S. Bellet
Proc. ASME. PVP2002, Emerging Technologies in Fluids, Structures and Fluid Structure Interactions: Volume 1, Fluid Dynamics, Fluid Structure Interaction, and High Explosive Detonation, 59-64, August 5–9, 2002
Publisher: American Society of Mechanical Engineers
Paper No: PVP2002-1461
https://doi.org/10.1115/PVP2002-1461
View Paper titled, CFD-Tool for Thermal-Hydraulics Pressurised Thermal Shock Analysis: Qualification of the Code_Saturne
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Topics: Computational fluid dynamics, Thermal hydraulics, Thermal shock, Temperature, Water, Fluids, Reactor vessels, Safety, Transients (Dynamics)
Proceedings Papers

The Effect of Pressure Relief Valve Blowdown and Fire Conditions on the Thermo-Hydraulics Within a Pressure Vessel

J. D. J. VanderSteen, A. M. Birk
Proc. ASME. PVP2002, Emerging Technologies in Fluids, Structures and Fluid Structure Interactions: Volume 2, Shock, Wave Propagation, Tube Bundle Dynamics, and Structural Dynamics, 153-162, August 5–9, 2002
Publisher: American Society of Mechanical Engineers
Paper No: PVP2002-1498
https://doi.org/10.1115/PVP2002-1498
View Paper titled, The Effect of Pressure Relief Valve Blowdown and Fire Conditions on the Thermo-Hydraulics Within a Pressure Vessel
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Topics: Fire, Pressure vessels, Relief valves, Thermal hydraulics, Pressure, Energy storage, Failure, Rupture, Accidents, Computers
Proceedings Papers

Application of Arbitrary Lagrange Euler Formulations to Flow-Induced Vibration Problems

Z. Bendjeddou, E. Longatte, M. Souli
Proc. ASME. PVP2002, Emerging Technologies in Fluids, Structures and Fluid Structure Interactions: Volume 2, Shock, Wave Propagation, Tube Bundle Dynamics, and Structural Dynamics, 225-233, August 5–9, 2002
Publisher: American Society of Mechanical Engineers
Paper No: PVP2002-1508
https://doi.org/10.1115/PVP2002-1508
View Paper titled, Application of Arbitrary Lagrange Euler Formulations to Flow-Induced Vibration Problems
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Topics: Flow-induced vibrations, Fluids, Flow (Dynamics), Vibration, Cross-flow, Turbulence, Computation, Computational fluid dynamics, Computer simulation, Damage
Proceedings Papers

Numerical Simulation of Non-Premixed Diffusion Flame and Reaction Product Aerosol Behavior in Liquid Metal Pool Combustion

Akira Yamaguchi, Yuji Tajima
Proc. ASME. PVP2002, Computational Technologies for Fluid/Thermal/Structural/Chemical Systems With Industrial Applications, Volume 1, 181-189, August 5–9, 2002
Publisher: American Society of Mechanical Engineers
Paper No: PVP2002-1550
https://doi.org/10.1115/PVP2002-1550
View Paper titled, Numerical Simulation of Non-Premixed Diffusion Flame and Reaction Product Aerosol Behavior in Liquid Metal Pool Combustion
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Topics: Aerosols, Combustion, Computer simulation, Diffusion flames, Liquid metals, Sodium, Flames, Temperature, Chemical reactions, Computation
Proceedings Papers

The Impact of an Improved Flaw Model on a Pressurized Thermal Shock Evaluation

T. L. Dickson, F. A. Simonen
Proc. ASME. PVP2002, Fatigue, Fracture and Damage Analysis, Volume 2, 125-131, August 5–9, 2002
Publisher: American Society of Mechanical Engineers
Paper No: PVP2002-1360
https://doi.org/10.1115/PVP2002-1360
View Paper titled, The Impact of an Improved Flaw Model on a Pressurized Thermal Shock Evaluation
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Topics: Thermal shock, Pressurized water reactors, Regulations, Human reliability analysis, Manufacturing, Uncertainty, Base metals, Computers, Embrittlement, Failure
Proceedings Papers

Engineered Security Measures of Nuclear Power Plants

F. J. Moody
Proc. ASME. PVP2003, Pressure Vessel and Piping Codes and Standards, 293, July 20–24, 2003
Publisher: American Society of Mechanical Engineers
Paper No: PVP2003-1808
https://doi.org/10.1115/PVP2003-1808
View Paper titled, Engineered Security Measures of Nuclear Power Plants
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Topics: Nuclear power stations, Security, Accidents, Safety, Containment, Failure, Errors, Thermal hydraulics, Coolants, Damage
Proceedings Papers

Evolution of the Thermal Hydraulics Design Methodologies for the European Pressurized Reactor (EPR) Vessel

Serge Bellet, Nicolas Goreaud, Norbert Nicaise
Proc. ASME. PVP2004, Emerging Technology in Fluids, Structures, and Fluid Structure Interactions: Volume 2, Dynamics of Explosive Detonation, Materials and Structures, Structural Mechanics and Design, 109-124, July 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: PVP2004-2889
https://doi.org/10.1115/PVP2004-2889
View Paper titled, Evolution of the Thermal Hydraulics Design Methodologies for the European Pressurized Reactor (EPR) Vessel
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Topics: Design, European pressurized reactors, Hydraulics, Reactor vessels, Thermal hydraulics, Vessels