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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
View Paper titled, Large-Scale Parametric Modeling of Spent Nuclear Fuel Dynamics in the 30 cm Package Drop Scenario
Click here to open pdf in another window PDF for Large-Scale Parametric Modeling of Spent Nuclear Fuel Dynamics in the 30 cm Package Drop Scenario
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
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A028, July 17–22, 2022
Paper No: PVP2022-84353
DOI: https://doi.org/10.1115/PVP2022-84353
View Paper titled, An Estimate of Spent Nuclear Fuel Mechanical Loads in the General 30 cm Package Drop Scenario
Click here to open pdf in another window PDF for An Estimate of Spent Nuclear Fuel Mechanical Loads in the General 30 cm Package Drop Scenario
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
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A017, July 17–22, 2022
Paper No: PVP2022-83156
DOI: https://doi.org/10.1115/PVP2022-83156
View Paper titled, Investigation Into Degradation of a Pilot Operated Pressure Relief Valve Main Seat During Development Testing
Click here to open pdf in another window PDF for Investigation Into Degradation of a Pilot Operated Pressure Relief Valve Main Seat During Development Testing
Topics: Corrosion, Damage, Relief valves, Testing, Valves, Cobalt alloys, Erosion, Failure, Flow (Dynamics), Leakage
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
View Paper titled, 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
Click here to open pdf in another window PDF for 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
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
View Paper titled, 3D Simulation of Propagation Induced by Primary Water Stress Corrosion Cracking for Defect Tolerance Analysis of Dissimilar Metal Welds
Click here to open pdf in another window PDF for 3D Simulation of Propagation Induced by Primary Water Stress Corrosion Cracking for Defect Tolerance Analysis of Dissimilar Metal Welds
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
View Paper titled, Experimental and Numerical Assessment of Weld Residual Stresses in Dissimilar Metal Weld of Reactor Pressure Vessel Nozzles
Click here to open pdf in another window PDF for Experimental and Numerical Assessment of Weld Residual Stresses in Dissimilar Metal Weld of Reactor Pressure Vessel Nozzles
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
View Paper titled, Revision of the Annex Z V Concerning the Calculation of Bolted Joints in the French Nuclear Code RCC-M®
Click here to open pdf in another window PDF for Revision of the Annex Z V Concerning the Calculation of Bolted Joints in the French Nuclear Code RCC-M®
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
View Paper titled, Impact of Thermal Ageing Embrittlement on Westinghouse and Combustion Engineering-Designed Pressurized Water Reactor Pressurizers Based on Pressure-Temperature Limit Comparison
Click here to open pdf in another window PDF for Impact of Thermal Ageing Embrittlement on Westinghouse and Combustion Engineering-Designed Pressurized Water Reactor Pressurizers Based on Pressure-Temperature Limit Comparison
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
View Paper titled, Development of a Robust Procedure for the Evaluation of Striation Spacings in Low Cycle Fatigue Specimens Tested in a Simulated PWR Environment
Click here to open pdf in another window PDF for Development of a Robust Procedure for the Evaluation of Striation Spacings in Low Cycle Fatigue Specimens Tested in a Simulated PWR Environment
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
View Paper titled, Thermomechanical Fatigue Initiation in Nuclear Grades of Austenitic Stainless Steel Using Plant Realistic Loading
Click here to open pdf in another window PDF for Thermomechanical Fatigue Initiation in Nuclear Grades of Austenitic Stainless Steel Using Plant Realistic Loading
Topics: ASME Standards, Calibration, Cracking (Materials), Cycles, Eddies (Fluid dynamics), Eddy currents (Electricity), Electrical discharge machining, Fatigue, Fatigue cracks, Fatigue life
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
View Paper titled, Development of Mini-Compact Tension Specimen Fabrication and Test Methods in Hot Cell for Post-Irradiation Examination of Reactor Pressure Vessel Steels
Click here to open pdf in another window PDF for Development of Mini-Compact Tension Specimen Fabrication and Test Methods in Hot Cell for Post-Irradiation Examination of Reactor Pressure Vessel Steels
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
View Paper titled, European Project ATLAS+: Large Scale Fracture Mechanics Tests on Ferritic Pipes
Click here to open pdf in another window PDF for European Project ATLAS+: Large Scale Fracture Mechanics Tests on Ferritic Pipes
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
View Paper titled, 30 CM Horizontal Drop of a Surrogate 17x17 PWR Fuel Assembly
Click here to open pdf in another window PDF for 30 CM Horizontal Drop of a Surrogate 17x17 PWR Fuel Assembly
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
View Paper titled, An Update of the Assessment Methodology for Civil Ageing Management for LTO/CSO Based on International Standards and Engineering Judgement
Click here to open pdf in another window PDF for An Update of the Assessment Methodology for Civil Ageing Management for LTO/CSO Based on International Standards and Engineering Judgement
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
View Paper titled, Design by Analysis, Codes, Standards and Rules on EAF - Applicability to Stainless Steels in PWR Primary Piping
Click here to open pdf in another window PDF for Design by Analysis, Codes, Standards and Rules on EAF - Applicability to Stainless Steels in PWR Primary Piping
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
View Paper titled, Technical Basis for Increased Inspection Interval of Cold Leg Pressurized Water Reactor Dissimilar Metal Welds Using xLPR
Click here to open pdf in another window PDF for Technical Basis for Increased Inspection Interval of Cold Leg Pressurized Water Reactor Dissimilar Metal Welds Using xLPR
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
View Paper titled, A Method for Investigating Multi-Axial Fatigue in a PWR Environment
Click here to open pdf in another window PDF for A Method for Investigating Multi-Axial Fatigue in a PWR Environment
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
View Paper titled, Negative R Fatigue Short Crack Growth Rate Testing on Austenitic Stainless Steels
Click here to open pdf in another window PDF for Negative R Fatigue Short Crack Growth Rate Testing on Austenitic Stainless Steels
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
View Paper titled, Technical Basis for Revision of Code Case N-809 on Reference Fatigue Crack Growth Curves for Austenitic Stainless Steels in Pressurized Water Reactor Environments
Click here to open pdf in another window PDF for Technical Basis for Revision of Code Case N-809 on Reference Fatigue Crack Growth Curves for Austenitic Stainless Steels in Pressurized Water Reactor Environments
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
View Paper titled, A Fatigue Crack Growth Model for Type 304 Austenitic Stainless Steels In a Pressurized Water Reactor Environment
Click here to open pdf in another window PDF for A Fatigue Crack Growth Model for Type 304 Austenitic Stainless Steels In a Pressurized Water Reactor Environment
Topics: Fatigue cracks, Pressurized water reactors, Stainless steel