Topics: Cracking (Materials) , Fracture (Process) , Hydrogen , Pipelines , Steel , Welded joints , Fracture (Materials) , Plates (structures) , Absorption , Arc welding

Determination of Discharge Coefficients for Hydraulic Sparger Design

Walter Boyd Gregg, David E. Werth, Carl Frizzell

PVP 2003; 45-51doi:https://doi.org/10.1115/PVP2003-2183

Abstract

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Topics: Design , Discharge coefficient , Flow (Dynamics) , Pressure , Cooling towers , Engineers , Manifolds , Open channels (Hydraulics) , Shapes

Effects of Inline Rotating Component on Piping System Dynamic Characteristics

Zakaria N. Ibrahim

PVP 2003; 53-61doi:https://doi.org/10.1115/PVP2003-2184

Abstract

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Topics: Piping systems , Eigenvalues , Degrees of freedom , Inertia (Mechanics) , System dynamics , Excitation , Mode shapes , Momentum

Deformation Relaxation: A Finite Element Optimization Method for Tee

Shijun Wang, Jinjuan Zhao

PVP 2003; 63-68doi:https://doi.org/10.1115/PVP2003-2185

Abstract

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Topics: Deformation , Finite element analysis , Optimization , Relaxation (Physics) , Stress , Displacement , Finite element model , Pipes , Reliability , Shapes

An Investigation Into the Feasibility of Environmental Fatigue Design for APR 1400 Primary Components and Piping With a 60 Year Design Life

J.-S. Park, J.-M. Kim, G.-S. Kim, T.-S. Choi

PVP 2003; 69-76doi:https://doi.org/10.1115/PVP2003-2186

Abstract

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Topics: Design , Fatigue design , Pipes , Fatigue , Alloy steel , ASME Standards , Nozzles , Nuclear reactor coolants , Reactor vessels , Stainless steel

CFD-Tool for Assessment of the Reactor Pressure Vessel Integrity in Pressure Thermal Shock Conditions for Lifetime Evaluation: Methodology and Qualification Task of the EDF Numerical Tools

A. Martin, F. Beaud, F. Ternon Morin, T. Veneau

PVP 2003; 79-89doi:https://doi.org/10.1115/PVP2003-2187

Abstract

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Topics: Computational fluid dynamics , Pressure , Reactor vessels , Thermal shock , Cooling , Temperature , Transients (Dynamics) , Vessels , Computation , Emergencies

PWR Nuclear Power Plants Reactor Vessel and Coolant System Cast Duplex Stainless Steel Elbows: New Results in Integrity Analysis

G. Bezdikian, C. Faidy, P. Cambefort, D. Moinereau

PVP 2003; 91-103doi:https://doi.org/10.1115/PVP2003-2188

Abstract

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Topics: Coolants , Nuclear power stations , Pressurized water reactors , Reactor vessels , Stainless steel , Computation , Finite element analysis , Nuclear reactor coolants , Databases , Ductility

The Sensitivity of Pressurized Thermal Shock Analysis Results to Alternative Models for Weld Flaw Distributions

T. L. Dickson, F. A. Simonen

PVP 2003; 105-112doi:https://doi.org/10.1115/PVP2003-2189

Abstract

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Topics: Thermal shock , Regulations , Risk , Vessels , Databases , Relaxation (Physics) , Base metals , Dimensions , Failure , Forging

Deterministic and Probabilistic Assessments of the Reactor Pressure Vessel Structural Integrity: Benchmark Comparisons

Silvia Turato, Vincent Venturini, Eric Meister, B. Richard Bass, Terry L. Dickson, Claud E. Pugh

PVP 2003; 113-122doi:https://doi.org/10.1115/PVP2003-2190

Abstract

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Topics: Accidents , Braking , Coolants , Fracture mechanics , Nuclear reactors , Pressure vessels , Reactor vessels , Safety , Transients (Dynamics) , Vessels

Presentation of a Numerical 3D Approach to Tackle Thermal Striping in a PWR Nuclear T-Junction

Christophe Pe´niguel, Marc Sakiz, Sofiane Benhamadouche, Jean-Michel Stephan, Carine Vindeirinho

PVP 2003; 125-132doi:https://doi.org/10.1115/PVP2003-2191

Abstract

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Topics: Junctions , Pressurized water reactors , Piping systems , Computation , Computational fluid dynamics , Finite element analysis , Fluids , Heat , Large eddy simulation , Stress

Fatigue Crack Initiation in Pressure Vessel Steels Using a Distance Parameter

Somnath Chattopadhyay

PVP 2003; 133-139doi:https://doi.org/10.1115/PVP2003-2192

Abstract

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Topics: Fatigue cracks , Pressure vessels , Steel , Fracture (Materials) , Fatigue design , Fracture mechanics , Plasticity , Stress

Proposal of Determination Procedure About Fatigue Safety Factors for Arbitrary Best Fit Curves

Nobuchika Kawasaki

PVP 2003; 141-148doi:https://doi.org/10.1115/PVP2003-2193

Abstract

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Topics: Fatigue , Safety , Databases , Pipes , Vessels , Fatigue testing , Finishes

Code Case 2286 Applied to the Design of Pressure Vessels

Kanhaiya L. Bardia, Kim Nguyen, Manfred Lengsfeld, Donald G. LaBounty, Bernie Au

PVP 2003; 151-157doi:https://doi.org/10.1115/PVP2003-2194

Abstract

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Topics: Design , Pressure vessels , ASME Standards , Compressive stress , ASME Boiler and Pressure Vessel Code , Cylinders , External pressure , Petrochemicals , Shells , Vessels

Design of an Optimum I-Beam Reinforcement for an API 620 Tank

Yogeshwar Hari, Ram Munjal, Namit Singh

PVP 2003; 159-165doi:https://doi.org/10.1115/PVP2003-2195

Abstract

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Topics: American Petroleum Institute , Design , Shells , Computer software , Finite element analysis , Stress , Dimensions , ASME Standards

Considerations in the Design and Analysis of an ASME Section VIII, Div. 2 Reactor Support Skirt

Dennis K. Williams, Trevor G. Seipp

PVP 2003; 167-174doi:https://doi.org/10.1115/PVP2003-2196

Abstract

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Topics: Design , Stress , Finite element analysis , Heat transfer , Vessels , Boundary-value problems , Displacement , Reactor vessels , Shells , Concretes

Qualification of a Jacketed Vessel Using Finite Element Analysis

Yogeshwar Hari, Ram Munjal, Chawki Obeid

PVP 2003; 175-182doi:https://doi.org/10.1115/PVP2003-2197

Abstract

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Topics: Finite element analysis , Vessels , External pressure , Design , Pressure , Dimensions , Fluids , Heat , Annulus , Boilers

All Years

Investigation of Stress Indices and Directional Loading of Eccentric Reducers

Relaxed Hanger Spans for Non-Critical Piping

Hydrogen Induced Cracking of Welds in Steel Pipelines

Determination of Discharge Coefficients for Hydraulic Sparger Design

Effects of Inline Rotating Component on Piping System Dynamic Characteristics

Deformation Relaxation: A Finite Element Optimization Method for Tee

An Investigation Into the Feasibility of Environmental Fatigue Design for APR 1400 Primary Components and Piping With a 60 Year Design Life

CFD-Tool for Assessment of the Reactor Pressure Vessel Integrity in Pressure Thermal Shock Conditions for Lifetime Evaluation: Methodology and Qualification Task of the EDF Numerical Tools

PWR Nuclear Power Plants Reactor Vessel and Coolant System Cast Duplex Stainless Steel Elbows: New Results in Integrity Analysis

The Sensitivity of Pressurized Thermal Shock Analysis Results to Alternative Models for Weld Flaw Distributions

Deterministic and Probabilistic Assessments of the Reactor Pressure Vessel Structural Integrity: Benchmark Comparisons

Presentation of a Numerical 3D Approach to Tackle Thermal Striping in a PWR Nuclear T-Junction

Fatigue Crack Initiation in Pressure Vessel Steels Using a Distance Parameter

Proposal of Determination Procedure About Fatigue Safety Factors for Arbitrary Best Fit Curves

Code Case 2286 Applied to the Design of Pressure Vessels

Design of an Optimum I-Beam Reinforcement for an API 620 Tank

Considerations in the Design and Analysis of an ASME Section VIII, Div. 2 Reactor Support Skirt

Qualification of a Jacketed Vessel Using Finite Element Analysis

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