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Proceedings Papers

The Development of a New Method to Compare the Fatigue Crack Growth Rates of Austenitic Stainless Steel Operating in a PWR Primary Coolant Subjected to Plant Realistic Temperature Loading

Benjamin Howe, Fabio Scenini, Grace Burke, Jonathan Mann

Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A011, July 17–22, 2022

Paper No: PVP2022-84208

DOI: https://doi.org/10.1115/PVP2022-84208

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Topics: Coolants, Fatigue, Fatigue cracks, Pressurized water reactors, Stainless steel, Temperature

Proceedings Papers

Advanced Structural Integrity Assessment Tools for Safe Long Term Operation (ATLAS+)

Sebastian Lindqvist, Anna Dahl, Mike Smith, Arnaud Blouin, Peter Dillström, Szabolcs Szavai, Tomas Nicak

Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A033, July 17–22, 2022

Paper No: PVP2022-80693

DOI: https://doi.org/10.1115/PVP2022-80693

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Topics: Coolants, Fracture mechanics, Materials properties, Nuclear reactor coolants, Nuclear reactors, Piping systems, Pressure, Reactor vessels, Residual stresses, Safety

Proceedings Papers

ATLAS+ European Project - General Method for the Components J-R Curve Derivation

Tomas Nicak, Arnaud Blouin, Stephane Marie, Olivier Ancelet

Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A039, July 17–22, 2022

Paper No: PVP2022-84853

DOI: https://doi.org/10.1115/PVP2022-84853

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Topics: Coolants, Fracture (Materials), Fracture mechanics, Geometry, Junctions, Materials properties, Nuclear reactors, Pipes, Pressure, Pressure vessels

Proceedings Papers

Advanced Structural Integrity Assessment Tools for Safe Long Term Operation - ATLAS+ Project: Status of the Activities of the WP3 on Modelling in 2020 & 2021

Arnaud Blouin, Stéphane Marie, Tomas Nicak, Antti Timperi, Peter Gill

Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A037, July 17–22, 2022

Paper No: PVP2022-84842

DOI: https://doi.org/10.1115/PVP2022-84842

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Topics: Coolants, Fracture (Materials), Fracture toughness, Leak-before-break, Modeling, Nuclear reactors, Pipes, Pressure, Residual stresses

Proceedings Papers

Ductile Tearing Prediction of Ferritic Pipes by GTN Model for ATLAS+ European Project (Report 2)

Satoshi Kumagai, Kiminobu Hojo, Takatoshi Hirota, Keiji Kawanishi

Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A036, July 17–22, 2022

Paper No: PVP2022-84554

DOI: https://doi.org/10.1115/PVP2022-84554

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Topics: Ductile fracture, Finite element analysis, Pipes, Fracture (Materials), Coolants, Damage mechanics, Errors, Fracture mechanics, Nuclear reactors, Pressure

Proceedings Papers

Experimental Investigation of Jet Cross-Flow Induced Vibration of a Rod Bundle

Ibrahim Gad-el-Hak, Njuki Mureithi, Kostas Karazis, Gary Williams

Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T04A014, July 13–15, 2021

Paper No: PVP2021-65000

DOI: https://doi.org/10.1115/PVP2021-65000

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Topics: Accidents, Coolants, Cross-flow, Fuel rods, Jets, Pressurized water reactors, Vibration

Proceedings Papers

Investigation of the Irradiation Effect on the Dynamics of Nuclear Fuel Bundles

Osama Elbanhawy, Marwan Hassan, Atef Mohany, Hossam Kishawy

Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T04A007, July 13–15, 2021

Paper No: PVP2021-62412

DOI: https://doi.org/10.1115/PVP2021-62412

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Topics: Dynamics (Mechanics), Fuel rods, Irradiation (Radiation exposure), Fuels, Flow (Dynamics), Constitutive equations, Coolants, Dynamic response, Mechanical properties, Pressure

Proceedings Papers

Advanced Structural Integrity Assessment Tools for Safe Long Term Operation - ATLAS+ Project: Status of the Activities of the WP3 on Modelling in 2021

Arnaud Blouin, Stéphane Marie, Tomas Nicak, Antti Timperi, Peter Gill

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A029, July 13–15, 2021

Paper No: PVP2021-62010

DOI: https://doi.org/10.1115/PVP2021-62010

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Topics: Coolants, Fracture (Materials), Fracture toughness, Leak-before-break, Modeling, Nuclear reactors, Pipes, Pressure, Residual stresses

Proceedings Papers

Comparison of International Codes for a Fatigue Crack Growth Flaw Tolerance Sample Problem

Gary L. Stevens

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A008, July 13–15, 2021

Paper No: PVP2021-61651

DOI: https://doi.org/10.1115/PVP2021-61651

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Topics: Fatigue cracks, ASME Standards, Pressurized water reactors, Coolants, Electricity (Physics), Engineering standards, Fatigue, Japan Society of Mechanical Engineers, JSME Standards, Pipes

Proceedings Papers

Comparative Evaluation of Plastic Design Methods for Fatigue Assessment of a Nuclear Class 1 Piping Nozzle

David M. Clarkson, Christopher D. Bell, Donald Mackenzie

Proc. ASME. PVP2020, Volume 3: Design and Analysis, V003T03A043, August 3, 2020

Paper No: PVP2020-21271

DOI: https://doi.org/10.1115/PVP2020-21271

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Topics: Design methodology, Fatigue, Nozzles, Pipes, Design, Finite element analysis, ASME Boiler and Pressure Vessel Code, Pressurized water reactors, Stress, Coolants

Proceedings Papers

Crack Propagation Modeling in a PWR Under PTS Using XFEM

Diego F. Mora, Markus Niffenegger, Roman Mukin

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A001, August 3, 2020

Paper No: PVP2020-21026

DOI: https://doi.org/10.1115/PVP2020-21026

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Topics: Crack propagation, Modeling, Pressurized water reactors, Fracture (Materials), Damage, Finite element analysis, Fracture toughness, Accidents, Cooling, Simulation

Proceedings Papers

Advanced Structural Integrity Assessment Tools for Safe Long Term Operation: ATLAS+ Project — Status of the Activities of the WP3 on Modelling in 2020

Arnaud Blouin, Stéphane Marie, Tomas Nicak, Antti Timperi, Peter Gill

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A046, August 3, 2020

Paper No: PVP2020-21551

DOI: https://doi.org/10.1115/PVP2020-21551

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Topics: Coolants, Fracture (Materials), Fracture toughness, Leak-before-break, Modeling, Nuclear reactors, Pipes, Pressure, Residual stresses

Proceedings Papers

Ductile Tearing Prediction of Ferritic Pipe Material by GTN Model for ATLAS+ European Project

Kiminobu Hojo, Takatoshi Hirota, Naoki Ogawa, Satoshi Kumagai

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A047, August 3, 2020

Paper No: PVP2020-21645

DOI: https://doi.org/10.1115/PVP2020-21645

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Topics: Pipes, Fracture (Materials), Fracture (Process), Coolants, Ductile fracture, Fracture mechanics, Nuclear reactors, Pressure, Simulation, Stress

Proceedings Papers

Elimination of BWR Mark I Program Primary Containment Drywell-to-Wetwell Differential Pressure

Raymond M. Pace, Jason Ritzel

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A045, August 3, 2020

Paper No: PVP2020-21001

DOI: https://doi.org/10.1115/PVP2020-21001

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Topics: Boiling water reactors, Containment, Pressure, Vents, Accidents, Nitrogen, Water, Control rooms, Filters, Pipes

Proceedings Papers

Development of Design Method for High Temperature Nuclear Reactor Cladded Components

B. Barua, M. C. Messner, R. I. Jetter, T.-L. Sham

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A067, August 3, 2020

Paper No: PVP2020-21469

DOI: https://doi.org/10.1115/PVP2020-21469

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Topics: Design methodology, High temperature, Nuclear reactors, Design, Coolants, Corrosion resistant materials, Corrosion, Creep, Failure, Finite element analysis

Proceedings Papers

SCC Growth Prediction for Surface Crack in Welded Joint Using Advanced FEA

Takuya Ogawa, Masao Itatani, Takahiro Hayashi, Toshiyuki Saito

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A080, August 3, 2020

Paper No: PVP2020-21670

DOI: https://doi.org/10.1115/PVP2020-21670

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Topics: Finite element analysis, Surface cracks, Welded joints, Fracture (Materials), Fracture (Process), Shapes, Fitness-for-service, Metals, Stainless steel, Base metals

Proceedings Papers

Finite Element Verification of Engineering Equations for Prediction of Structural Strength of Annulus Spacers in CANDU Nuclear Reactors

Preeti Doddihal, Dennis Kawa, Douglas Scarth, Yu Chen

Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A013, July 14–19, 2019

Paper No: PVP2019-93671

DOI: https://doi.org/10.1115/PVP2019-93671

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Topics: Annulus, Finite element analysis, Nuclear reactors, Fracture (Materials), Fracture (Process), Strips, Fuels, Irradiation (Radiation exposure), Pressure, Stress

Proceedings Papers

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

Patrick Le Delliou, Dominique Moinereau, Myriam Bourgeois, Szabolcs Szavai

Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A043, July 14–19, 2019

Paper No: PVP2019-93505

DOI: https://doi.org/10.1115/PVP2019-93505

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Topics: Pipes, Fracture mechanics, Steel, Coolants, Design, Materials characterization, Materials properties, Metals, Nuclear reactors, Pressure

Proceedings Papers

Advances Towards Elastic-Perfectly Plastic Simulation of the Core of Printed Circuit Heat Exchangers

Alon Katz, Devesh Ranjan

Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A093, July 14–19, 2019

Paper No: PVP2019-93807

DOI: https://doi.org/10.1115/PVP2019-93807

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Topics: Circuits, Heat exchangers, Simulation, Stress, Algorithms, ASME Standards, Brayton cycle, Computer simulation, Computer software, Coolants

Proceedings Papers

Vibration of a High Energy PWR Piping System due to Vibro-Acoustic Coupling: Evaluation and Mitigation

Gregory A. Meyer, Timothy K. Meneely, Jeremy R. Koether, Stephen D. Smith, David C. DiBasilio

Proc. ASME. PVP2019, Volume 4: Fluid-Structure Interaction, V004T04A021, July 14–19, 2019

Paper No: PVP2019-93594

DOI: https://doi.org/10.1115/PVP2019-93594

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Topics: Acoustics, Piping systems, Pressurized water reactors, Vibration, Pipes, Flow (Dynamics), Resonance, Boiling water reactors, Excitation, Junctions

NARROW

The Development of a New Method to Compare the Fatigue Crack Growth Rates of Austenitic Stainless Steel Operating in a PWR Primary Coolant Subjected to Plant Realistic Temperature Loading

Advanced Structural Integrity Assessment Tools for Safe Long Term Operation (ATLAS+)

ATLAS+ European Project - General Method for the Components J-R Curve Derivation

Advanced Structural Integrity Assessment Tools for Safe Long Term Operation - ATLAS+ Project: Status of the Activities of the WP3 on Modelling in 2020 & 2021

Ductile Tearing Prediction of Ferritic Pipes by GTN Model for ATLAS+ European Project (Report 2)

Experimental Investigation of Jet Cross-Flow Induced Vibration of a Rod Bundle

Investigation of the Irradiation Effect on the Dynamics of Nuclear Fuel Bundles

Advanced Structural Integrity Assessment Tools for Safe Long Term Operation - ATLAS+ Project: Status of the Activities of the WP3 on Modelling in 2021

Comparison of International Codes for a Fatigue Crack Growth Flaw Tolerance Sample Problem

Comparative Evaluation of Plastic Design Methods for Fatigue Assessment of a Nuclear Class 1 Piping Nozzle

Crack Propagation Modeling in a PWR Under PTS Using XFEM

Advanced Structural Integrity Assessment Tools for Safe Long Term Operation: ATLAS+ Project — Status of the Activities of the WP3 on Modelling in 2020

Ductile Tearing Prediction of Ferritic Pipe Material by GTN Model for ATLAS+ European Project

Elimination of BWR Mark I Program Primary Containment Drywell-to-Wetwell Differential Pressure

Development of Design Method for High Temperature Nuclear Reactor Cladded Components

SCC Growth Prediction for Surface Crack in Welded Joint Using Advanced FEA

Finite Element Verification of Engineering Equations for Prediction of Structural Strength of Annulus Spacers in CANDU Nuclear Reactors

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

Advances Towards Elastic-Perfectly Plastic Simulation of the Core of Printed Circuit Heat Exchangers

Vibration of a High Energy PWR Piping System due to Vibro-Acoustic Coupling: Evaluation and Mitigation

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