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Proceedings Papers

Post-Test Analysis of a Large Scale Mock-Up Test Performed in the European Project ATLAS+

Tomas Nicak, Alexey Rempel

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A027, July 13–15, 2021

Paper No: PVP2021-60495

DOI: https://doi.org/10.1115/PVP2021-60495

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Topics: Brittle fracture, Brittleness, Circuits, Crack propagation, Ductile fracture, Feedwater, Fractography, Fracture (Materials), Fracture mechanics, Nuclear power stations

Proceedings Papers

European Project ATLAS+: Large Scale Fracture Mechanics Tests on Ferritic Pipes

Anna Dahl, Willy Vincent

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A028, July 13–15, 2021

Paper No: PVP2021-61834

DOI: https://doi.org/10.1115/PVP2021-61834

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Topics: Fracture mechanics, Pipes, Steel, Fracture (Materials), Design, Feedwater, Pressurized water reactors, Shapes, Stainless steel, Temperature

Proceedings Papers

Probabilistic Fracture Mechanics Evaluation of a BWR Feedwater Nozzle

Kevin K. L. Wong, Garivalde Dominguez, Do Jun Shim, Steven K. Richter

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A031, July 13–15, 2021

Paper No: PVP2021-62933

DOI: https://doi.org/10.1115/PVP2021-62933

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Topics: ASME Standards, Boiling water reactors, Feedwater, Fracture mechanics, Inspection, Nozzles, Shells

Proceedings Papers

European Project ATLAS+: Status of the WP1 Relative to the Experimental Program on Pipes and Specimens

Dominique Moinereau, Tomas Nicak, Anna Dahl

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A048, August 3, 2020

Paper No: PVP2020-21844

DOI: https://doi.org/10.1115/PVP2020-21844

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Topics: Pipes, Fracture (Materials), Fracture (Process), Stainless steel, Alloys, Feedwater, Materials properties, Pressurized water reactors, Steel

Proceedings Papers

Inspection Optimization Justification for PWR Main Steam and Feedwater Nozzles Using Probabilistic Fracture Mechanics

C. Lohse, D. J. Shim, D. Somasundaram, R. Grizzi, G. L. Stevens, T. Cinson

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A058, July 14–19, 2019

Paper No: PVP2019-93948

DOI: https://doi.org/10.1115/PVP2019-93948

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Topics: Feedwater, Fracture mechanics, Inspection, Nozzles, Optimization, Pressurized water reactors, Steam, ASME Standards, Welded joints, Boilers

Proceedings Papers

Effects of Initial Pressure and Length of a Broken Pipe on the Transient Hydraulic Loads Acting on Nuclear Steam Generator Tubes and Supports During Blowdown Following a Sudden Feedwater Pipe Break

Jong Chull Jo, Jae-Jun Jeong, Byong-Jo Yun

Proc. ASME. PVP2019, Volume 4: Fluid-Structure Interaction, V004T04A033, July 14–19, 2019

Paper No: PVP2019-93132

DOI: https://doi.org/10.1115/PVP2019-93132

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Topics: Feedwater, Nuclear reactor steam generators, Pipes, Pressure, Stress, Transients (Dynamics), Pressurized water reactors, Boilers, Flow (Dynamics), Unsteady flow

Proceedings Papers

Evaluation of Creep Properties of Alloy 690 Steam Generator Tubes at High Temperature Using Tube Specimen

Jongmin Kim, Woogon Kim, Minchul Kim

Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A018, July 14–19, 2019

Paper No: PVP2019-93498

DOI: https://doi.org/10.1115/PVP2019-93498

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Topics: Alloys, Boilers, Creep, High temperature, High temperature creep, Rupture, Accidents, Containment, Corrosion resistance, Failure

Proceedings Papers

Full Structural Weld Overlay on a Super Emergency Feedwater Nozzle at the Dukovany Nuclear Power Plant

Steven L. McCracken, Marek Palán, Pavel Mlynář, Nicholas Mohr

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A092, July 14–19, 2019

Paper No: PVP2019-93664

DOI: https://doi.org/10.1115/PVP2019-93664

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Topics: Emergencies, Feedwater, Nozzles, Nuclear power stations, Overlays (Materials engineering), Maintenance, Metals, ASME Standards, Boilers, Inspection

Proceedings Papers

Use of Stainless Steel Tubing in Boiling Applications for Shell and Tube Heat Exchangers

Sarah Radovcich, Cathleen Shargay, Kuntak Daru

Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A091, July 14–19, 2019

Paper No: PVP2019-93739

DOI: https://doi.org/10.1115/PVP2019-93739

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Topics: Boiling, Heat exchangers, Shells, Stainless steel, Tubing, Risk, Steam, Water, Failure, Alloy steel

Proceedings Papers

Fitness for Service Assessments on Cracked Heavy Wall Reactors

Jan Keltjens, Gys Van Zyl, Fahad Mudhayeq

Proc. ASME. PVP2018, Volume 3B: Design and Analysis, V03BT03A010, July 15–20, 2018

Paper No: PVP2018-84046

DOI: https://doi.org/10.1115/PVP2018-84046

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Topics: Fitness-for-service, Stress corrosion cracking, Alloy steel, Cracking (Materials), Downtime, Failure mechanisms, Feedwater, Fracture (Materials), Fracture (Process), Heat

Proceedings Papers

Sulfidation Rate Prediction on Tube-to-Tubesheet Joints in a Waste Heat Boiler in a Sulphur Plant

Feng Ju, Allen Miller, Simon Yuen, Brian Tkachyk

Proc. ASME. PVP2018, Volume 3B: Design and Analysis, V03BT03A020, July 15–20, 2018

Paper No: PVP2018-85070

DOI: https://doi.org/10.1115/PVP2018-85070

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Topics: Boilers, Sulfur, Waste heat, Design, Temperature, Metals, Tubular joints, Alloys, Carbon steel, Cladding systems (Building)

Proceedings Papers

Prediction of Transient Hydrodynamic Loads on the PWR Steam Generator Tubes at a Main Feed Water Line Break Accident

Jong Chull Jo, Jae Jun Jeong, Byong Jo Yun

Proc. ASME. PVP2018, Volume 4: Fluid-Structure Interaction, V004T04A019, July 15–20, 2018

Paper No: PVP2018-84152

DOI: https://doi.org/10.1115/PVP2018-84152

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Topics: Accidents, Boilers, Feedwater, Pressurized water reactors, Stress, Transients (Dynamics), Pipes, Computational fluid dynamics, Flow (Dynamics), Simulation

Proceedings Papers

Fitness-for-Service Assessment of an Injection Point in a Boiler Feed-Water Line Subjected to Corrosion

Takuyo Kaida, Masahiro Sasaki, Luis Alejandro Baldomir Gutierrez

Proc. ASME. PVP2018, Volume 7: Operations, Applications, and Components, V007T07A013, July 15–20, 2018

Paper No: PVP2018-85038

DOI: https://doi.org/10.1115/PVP2018-85038

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Topics: Corrosion, Feedwater, Fitness-for-service, Metals, Countermeasures, Design, Inspection, Pipes, Piping systems, Shapes

Proceedings Papers

Two- and Three-Dimensional Weld Residual Stress Analysis of a Weld Overlay Mockup of a VVER Feedwater Nozzle Dissimilar Metal Weld

Francis H. Ku, Steven L. McCracken

Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A082, July 15–20, 2018

Paper No: PVP2018-84981

DOI: https://doi.org/10.1115/PVP2018-84981

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Topics: Feedwater, Metals, Nozzles, Overlays (Materials engineering), Stress analysis (Engineering), Pressurized water reactors, Design, Water, Emergencies, Finite element analysis

Proceedings Papers

Design Modification to Mitigate the Reactor Inner Zone Inlet Header Temperature in a CANDU Reactor

Bing Li, Preston Tang, Khurram Khan, Akash Bhatia

Proc. ASME. PVP2017, Volume 3A: Design and Analysis, V03AT03A041, July 16–20, 2017

Paper No: PVP2017-65096

DOI: https://doi.org/10.1115/PVP2017-65096

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Topics: Design, Temperature, Economics , Feedwater, High pressure (Physics), High temperature, Risk, Safety

Proceedings Papers

A Comparative Fatigue Analysis Study Based on RCC-M Code and EN13-445 Standard Through Actual Test Cases

François Billon, Julien Halleguen

Proc. ASME. PVP2017, Volume 3B: Design and Analysis, V03BT03A012, July 16–20, 2017

Paper No: PVP2017-65530

DOI: https://doi.org/10.1115/PVP2017-65530

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Topics: Fatigue analysis, Shells, Nozzles, Welded joints, Base metals, Fatigue, Feedwater, Finite element model, Grinding, Nondestructive evaluation

Proceedings Papers

Numerical Simulation of a Highly Compressed Saturated Water Flashing Flow

Jong Chull Jo, Jae Jun Jeong, Byong Jo Yun, Frederick J. Moody

Proc. ASME. PVP2017, Volume 4: Fluid-Structure Interaction, V004T04A001, July 16–20, 2017

Paper No: PVP2017-65143

DOI: https://doi.org/10.1115/PVP2017-65143

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Topics: Computer simulation, Flashing, Flow (Dynamics), Water, Feedwater, Pipes, Accidents, Atmospheric pressure, Fluids, High pressure (Physics)

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

A Probability-Based Leak-Before-Break Application for Small Modular Reactors

Heqin Xu, Tamas Liszkai

Proc. ASME. PVP2015, Volume 3: Design and Analysis, V003T03A073, July 19–23, 2015

Paper No: PVP2015-45724

DOI: https://doi.org/10.1115/PVP2015-45724

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Topics: Leak-before-break, Probability, Small modular reactors, Pipes, Rupture, Design, Fracture (Materials), Piping systems, Dimensions, Fluids

Proceedings Papers

Fatigue Monitoring in the Context of Long-Term Operation of the Goesgen Nuclear Power Plant Using AREVA’s FAMOSi

Thomas Wermelinger, Florian Bruckmüller, Benedikt Heinz

Proc. ASME. PVP2015, Volume 7: Operations, Applications and Components, V007T07A016, July 19–23, 2015

Paper No: PVP2015-45272

DOI: https://doi.org/10.1115/PVP2015-45272

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Topics: Fatigue, Nuclear power stations, Stress, Boilers, Optimization, Sprays, Circuits, Cooling, Feedwater, Heating

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NARROW

Post-Test Analysis of a Large Scale Mock-Up Test Performed in the European Project ATLAS+

European Project ATLAS+: Large Scale Fracture Mechanics Tests on Ferritic Pipes

Probabilistic Fracture Mechanics Evaluation of a BWR Feedwater Nozzle

European Project ATLAS+: Status of the WP1 Relative to the Experimental Program on Pipes and Specimens

Inspection Optimization Justification for PWR Main Steam and Feedwater Nozzles Using Probabilistic Fracture Mechanics

Effects of Initial Pressure and Length of a Broken Pipe on the Transient Hydraulic Loads Acting on Nuclear Steam Generator Tubes and Supports During Blowdown Following a Sudden Feedwater Pipe Break

Evaluation of Creep Properties of Alloy 690 Steam Generator Tubes at High Temperature Using Tube Specimen

Full Structural Weld Overlay on a Super Emergency Feedwater Nozzle at the Dukovany Nuclear Power Plant

Use of Stainless Steel Tubing in Boiling Applications for Shell and Tube Heat Exchangers

Fitness for Service Assessments on Cracked Heavy Wall Reactors

Sulfidation Rate Prediction on Tube-to-Tubesheet Joints in a Waste Heat Boiler in a Sulphur Plant

Prediction of Transient Hydrodynamic Loads on the PWR Steam Generator Tubes at a Main Feed Water Line Break Accident

Fitness-for-Service Assessment of an Injection Point in a Boiler Feed-Water Line Subjected to Corrosion

Two- and Three-Dimensional Weld Residual Stress Analysis of a Weld Overlay Mockup of a VVER Feedwater Nozzle Dissimilar Metal Weld

Design Modification to Mitigate the Reactor Inner Zone Inlet Header Temperature in a CANDU Reactor

A Comparative Fatigue Analysis Study Based on RCC-M Code and EN13-445 Standard Through Actual Test Cases

Numerical Simulation of a Highly Compressed Saturated Water Flashing Flow

Traditional Versus New Technology Boiler Drum Water Level Instruments

A Probability-Based Leak-Before-Break Application for Small Modular Reactors

Fatigue Monitoring in the Context of Long-Term Operation of the Goesgen Nuclear Power Plant Using AREVA’s FAMOSi

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