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Proceedings Papers

Damage Evaluations for BWR Lower Head in Severe Accident Based on Multi-Physics Simulations

Jinya Katsuyama, Yoshihito Yamaguchi, Yoshiyuki Nemoto, Takuya Furuta, Yoshiyuki Kaji

Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A030, July 17–22, 2022

Paper No: PVP2022-84609

DOI: https://doi.org/10.1115/PVP2022-84609

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Topics: Accidents, Boiling water reactors, Creep, Damage, Physics, Radiation (Physics), Simulation, Thermal hydraulics

Proceedings Papers

A Flexible Tool for Modeling Thermal Loading in Printed Circuit Heat Exchangers

Ian W. Jentz, Mark H. Anderson

Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A092, July 14–19, 2019

Paper No: PVP2019-93773

DOI: https://doi.org/10.1115/PVP2019-93773

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Topics: Circuits, Heat exchangers, Modeling, Transients (Dynamics), Design, Nuclear power stations, ASME Boiler and Pressure Vessel Code, Construction, Creep, Fatigue

Proceedings Papers

XFEM and Standard Fracture-Mechanics Analyses of the Reactor Pressure Vessel Gösgen Based on Thermal-Hydraulics Input Data From KWU-MIX and CFD Analyses

Alexander Mutz, Tomas Nicak, Richard Trewin, Ingo Cremer

Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A044, July 14–19, 2019

Paper No: PVP2019-93564

DOI: https://doi.org/10.1115/PVP2019-93564

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Topics: Computational fluid dynamics, Fracture mechanics, Reactor vessels, Thermal hydraulics

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

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

Paper No: PVP2018-84534

DOI: https://doi.org/10.1115/PVP2018-84534

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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

Paper No: PVP2018-84553

DOI: https://doi.org/10.1115/PVP2018-84553

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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

Paper No: PVP2018-84923

DOI: https://doi.org/10.1115/PVP2018-84923

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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

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

Paper No: PVP2016-63443

DOI: https://doi.org/10.1115/PVP2016-63443

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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

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

Paper No: PVP2016-63459

DOI: https://doi.org/10.1115/PVP2016-63459

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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

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

Paper No: PVP2015-45156

DOI: https://doi.org/10.1115/PVP2015-45156

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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

Paper No: PVP2014-28645

DOI: https://doi.org/10.1115/PVP2014-28645

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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

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

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

Paper No: PVP2010-25606

DOI: https://doi.org/10.1115/PVP2010-25606

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Topics: Boilers, Flow (Dynamics), Pressure, Plates (structures), Two-phase flow, Refrigerants, Water, Computation, Computational methods, Heat

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

Paper No: PVP2009-77396

DOI: https://doi.org/10.1115/PVP2009-77396

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Topics: Carbon reinforced plastics, Computation, Computational methods, Emergencies, Fracture (Materials), Nozzles, Reactor vessels, Stress, Temperature, Thermal hydraulics

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

Paper No: PVP2009-77140

DOI: https://doi.org/10.1115/PVP2009-77140

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Topics: Boilers, Stress, Flow (Dynamics), Cooling, Heat transfer, Mechanical behavior, Modeling, Oscillations, Risk, Safety

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

Paper No: PVP2008-61804

DOI: https://doi.org/10.1115/PVP2008-61804

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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

Paper No: PVP2008-61717

DOI: https://doi.org/10.1115/PVP2008-61717

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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

Paper No: PVP2002-1461

DOI: https://doi.org/10.1115/PVP2002-1461

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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

Paper No: PVP2002-1498

DOI: https://doi.org/10.1115/PVP2002-1498

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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

Paper No: PVP2002-1508

DOI: https://doi.org/10.1115/PVP2002-1508

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Topics: Flow-induced vibrations, Fluids, Flow (Dynamics), Vibration, Cross-flow, Turbulence, Computation, Computational fluid dynamics, Computer simulation, Damage

NARROW

Damage Evaluations for BWR Lower Head in Severe Accident Based on Multi-Physics Simulations

A Flexible Tool for Modeling Thermal Loading in Printed Circuit Heat Exchangers

XFEM and Standard Fracture-Mechanics Analyses of the Reactor Pressure Vessel Gösgen Based on Thermal-Hydraulics Input Data From KWU-MIX and CFD Analyses

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

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

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

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

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

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

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

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

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

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

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

Loads Applied to Clogged Steam Generators Internal Structures

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

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

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

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

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

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