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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

3D Simulation of Propagation Induced by Primary Water Stress Corrosion Cracking for Defect Tolerance Analysis of Dissimilar Metal Welds

Pierre Dulieu, Valéry Lacroix

Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A036, July 17–22, 2022

Paper No: PVP2022-84667

DOI: https://doi.org/10.1115/PVP2022-84667

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Topics: Metals, Simulation, Stress corrosion cracking, Tolerance analysis, Water, Welded joints, Stress, Fracture (Materials), Accounting, Alloys

Proceedings Papers

Experimental and Numerical Assessment of Weld Residual Stresses in Dissimilar Metal Weld of Reactor Pressure Vessel Nozzles

Pierre Dulieu, Valéry Lacroix, Vratislav Mares, Larbi Arbaoui, Jean-Philippe Bournot

Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A082, July 17–22, 2022

Paper No: PVP2022-79529

DOI: https://doi.org/10.1115/PVP2022-79529

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Topics: Metals, Nozzles, Reactor vessels, Residual stresses, Stress, Welding, Heat, Simulation, Welded joints, Alloys

Proceedings Papers

Revision of the Annex Z V Concerning the Calculation of Bolted Joints in the French Nuclear Code RCC-M®

Hubert Lejeune, Philippe Rohart, Manuela Triay, Aurélien Di Rienzo

Proc. ASME. PVP2022, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T02A014, July 17–22, 2022

Paper No: PVP2022-81911

DOI: https://doi.org/10.1115/PVP2022-81911

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Topics: Bolted flanges, Bolted joints, Computational methods, Construction, Design, Electromagnetic scattering, Flanges, Gaskets, Graphite, Manufacturing

Proceedings Papers

Impact of Thermal Ageing Embrittlement on Westinghouse and Combustion Engineering-Designed Pressurized Water Reactor Pressurizers Based on Pressure-Temperature Limit Comparison

Alexandria M. Scott, Louis W. Turicik, J. Brian Hall, Anees Udyawar, Amy E. Freed, Elliot J. Long

Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A022, July 17–22, 2022

Paper No: PVP2022-85520

DOI: https://doi.org/10.1115/PVP2022-85520

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Topics: Combustion, Combustion engineering, Embrittlement, Pressure, Pressurized water reactors, Temperature

Proceedings Papers

Development of a Robust Procedure for the Evaluation of Striation Spacings in Low Cycle Fatigue Specimens Tested in a Simulated PWR Environment

Benjamin Howe, Jonathan Mann, Zaiqing Que, Caitlin Huotilainen, Fabio Scenini, Grace Burke

Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A035, July 17–22, 2022

Paper No: PVP2022-84027

DOI: https://doi.org/10.1115/PVP2022-84027

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Topics: Fatigue, Low cycle fatigue, Pressurized water reactors, Stainless steel

Proceedings Papers

Thermomechanical Fatigue Initiation in Nuclear Grades of Austenitic Stainless Steel Using Plant Realistic Loading

Glenn Trownson, Peter Gill, William Brayshaw, James Watson, Jonathan Mann

Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A023, July 17–22, 2022

Paper No: PVP2022-84760

DOI: https://doi.org/10.1115/PVP2022-84760

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Topics: ASME Standards, Calibration, Cracking (Materials), Cycles, Eddies (Fluid dynamics), Eddy currents (Electricity), Electrical discharge machining, Fatigue, Fatigue cracks, Fatigue life

Proceedings Papers

Large-Scale Parametric Modeling of Spent Nuclear Fuel Dynamics in the 30 cm Package Drop Scenario

Kevin Kadooka, James Fitzpatrick, Nicholas Klymyshyn

Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A030, July 17–22, 2022

Paper No: PVP2022-84747

DOI: https://doi.org/10.1115/PVP2022-84747

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Topics: Dynamics (Mechanics), Modeling, Spent nuclear fuels, Fuels, Manufacturing, Simulation, Stress, Boiling water reactors, Cladding systems (Building), Fuel rods

Proceedings Papers

An Estimate of Spent Nuclear Fuel Mechanical Loads in the General 30 cm Package Drop Scenario

Nicholas Klymyshyn, Kevin Kadooka, Casey Spitz, James Fitzpatrick

Paper No: PVP2022-84353

DOI: https://doi.org/10.1115/PVP2022-84353

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Topics: Spent nuclear fuels, Stress, Fuels, Manufacturing, Damage, Modeling, Boiling water reactors, Boundary element methods, Collaboration, Design

Proceedings Papers

Investigation Into Degradation of a Pilot Operated Pressure Relief Valve Main Seat During Development Testing

Martin Kane, Phil Thompson, David Stewart

Paper No: PVP2022-83156

DOI: https://doi.org/10.1115/PVP2022-83156

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Topics: Corrosion, Damage, Relief valves, Testing, Valves, Cobalt alloys, Erosion, Failure, Flow (Dynamics), Leakage

Proceedings Papers

Development of Mini-Compact Tension Specimen Fabrication and Test Methods in Hot Cell for Post-Irradiation Examination of Reactor Pressure Vessel Steels

Frideriki Naziris, Casper Versteylen, Frederick Frith, Marcel Bregman, Murthy Kolluri

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A064, July 13–15, 2021

Paper No: PVP2021-61027

DOI: https://doi.org/10.1115/PVP2021-61027

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Topics: Irradiation (Radiation exposure), Manufacturing, Reactor vessels, Steel, Tension, Testing, Geometry, Stress, ASTM International, Pressurized water reactors

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

30 CM Horizontal Drop of a Surrogate 17x17 PWR Fuel Assembly

Elena Kalinina, Doug Ammerman, Carissa Grey, Gregg Flores, Lucas Lujan, Sylvia Saltzstein, Danielle Michel

Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A022, July 13–15, 2021

Paper No: PVP2021-60533

DOI: https://doi.org/10.1115/PVP2021-60533

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Topics: Cladding systems (Building), Fuels, Manufacturing, Pressure, Pressurized water reactors, Spent nuclear fuels, Stress-strain curves, Arches, Bending (Stress), Blanks

Proceedings Papers

An Update of the Assessment Methodology for Civil Ageing Management for LTO/CSO Based on International Standards and Engineering Judgement

F. H. E. de Haan - de Wilde, M. J. Janssen

Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A008, July 13–15, 2021

Paper No: PVP2021-61499

DOI: https://doi.org/10.1115/PVP2021-61499

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Topics: Amperes, Concretes, Containment, Engineering standards, Finite element analysis, Maintenance, Modeling, Nuclear power stations, Nuclear reactors, Performance

Proceedings Papers

Design by Analysis, Codes, Standards and Rules on EAF - Applicability to Stainless Steels in PWR Primary Piping

Jussi Solin, Tommi Seppänen, Rami Vanninen, Erkki Pulkkinen, Petri Lemettinen

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A011, July 13–15, 2021

Paper No: PVP2021-62187

DOI: https://doi.org/10.1115/PVP2021-62187

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Topics: Design, Electric arc furnaces, Fatigue, Pipes, Pressurized water reactors, Stainless steel, ASME Boiler and Pressure Vessel Code, Engineering standards, Fatigue analysis, Life cycle management

Proceedings Papers

Technical Basis for Increased Inspection Interval of Cold Leg Pressurized Water Reactor Dissimilar Metal Welds Using xLPR

Chris Lohse, Do Jun Shim, Dilip Dedhia, Rohan Dutta, Nathan Glunt

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A030, July 13–15, 2021

Paper No: PVP2021-62560

DOI: https://doi.org/10.1115/PVP2021-62560

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Topics: Inspection, Metals, Pressurized water reactors, Welded joints, Fracture (Materials), Alloys, ASME Standards, Computers, Probability, Temperature

Proceedings Papers

A Method for Investigating Multi-Axial Fatigue in a PWR Environment

Peter Gill, Paul Onwuarolu, Russell Smith, Ben Coult, Mark Kirkham, Matt Sutcliffe, Karen Cooper, Tom Schofield, Colin Madew, Alec McLennan, Chris Currie

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A012, July 13–15, 2021

Paper No: PVP2021-62429

DOI: https://doi.org/10.1115/PVP2021-62429

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Topics: Fatigue, Pressurized water reactors, Stress, Fatigue testing, Cycles, Failure, Finite element analysis, Cracking (Materials), Fracture (Process), Design

Proceedings Papers

Negative R Fatigue Short Crack Growth Rate Testing on Austenitic Stainless Steels

Adam Griffiths, Peter Gill, Ben Coult, Jack Beswick, Norman Platts, Jonathan Mann, Chris Currie, Joe Airey

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A013, July 13–15, 2021

Paper No: PVP2021-62909

DOI: https://doi.org/10.1115/PVP2021-62909

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Topics: Fatigue, Fracture (Materials), Stainless steel, Testing, Grain size, Heat, Nucleation (Physics), Stress, Analytical methods, ASME Standards

Proceedings Papers

Technical Basis for Revision of Code Case N-809 on Reference Fatigue Crack Growth Curves for Austenitic Stainless Steels in Pressurized Water Reactor Environments

Russell C. Cipolla, Warren H. Bamford, Kiminobu Hojo, Yuichiro Nomura

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A001, July 13–15, 2021

Paper No: PVP2021-61728

DOI: https://doi.org/10.1115/PVP2021-61728

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Topics: Fatigue cracks, Pressurized water reactors, Stainless steel

Proceedings Papers

A Fatigue Crack Growth Model for Type 304 Austenitic Stainless Steels In a Pressurized Water Reactor Environment

Kathleen C. Barron, Denise J. Paraventi

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A015, July 13–15, 2021

Paper No: PVP2021-65973

DOI: https://doi.org/10.1115/PVP2021-65973

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Topics: Fatigue cracks, Pressurized water reactors, Stainless steel

2 3 4 5

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

3D Simulation of Propagation Induced by Primary Water Stress Corrosion Cracking for Defect Tolerance Analysis of Dissimilar Metal Welds

Experimental and Numerical Assessment of Weld Residual Stresses in Dissimilar Metal Weld of Reactor Pressure Vessel Nozzles

Revision of the Annex Z V Concerning the Calculation of Bolted Joints in the French Nuclear Code RCC-M®

Impact of Thermal Ageing Embrittlement on Westinghouse and Combustion Engineering-Designed Pressurized Water Reactor Pressurizers Based on Pressure-Temperature Limit Comparison

Development of a Robust Procedure for the Evaluation of Striation Spacings in Low Cycle Fatigue Specimens Tested in a Simulated PWR Environment

Thermomechanical Fatigue Initiation in Nuclear Grades of Austenitic Stainless Steel Using Plant Realistic Loading

Large-Scale Parametric Modeling of Spent Nuclear Fuel Dynamics in the 30 cm Package Drop Scenario

An Estimate of Spent Nuclear Fuel Mechanical Loads in the General 30 cm Package Drop Scenario

Investigation Into Degradation of a Pilot Operated Pressure Relief Valve Main Seat During Development Testing

Development of Mini-Compact Tension Specimen Fabrication and Test Methods in Hot Cell for Post-Irradiation Examination of Reactor Pressure Vessel Steels

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

30 CM Horizontal Drop of a Surrogate 17x17 PWR Fuel Assembly

An Update of the Assessment Methodology for Civil Ageing Management for LTO/CSO Based on International Standards and Engineering Judgement

Design by Analysis, Codes, Standards and Rules on EAF - Applicability to Stainless Steels in PWR Primary Piping

Technical Basis for Increased Inspection Interval of Cold Leg Pressurized Water Reactor Dissimilar Metal Welds Using xLPR

A Method for Investigating Multi-Axial Fatigue in a PWR Environment

Negative R Fatigue Short Crack Growth Rate Testing on Austenitic Stainless Steels

Technical Basis for Revision of Code Case N-809 on Reference Fatigue Crack Growth Curves for Austenitic Stainless Steels in Pressurized Water Reactor Environments

A Fatigue Crack Growth Model for Type 304 Austenitic Stainless Steels In a Pressurized Water Reactor Environment

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