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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

Practical Procedure of Test Temperature Selection for Mini-C(T) Master Curve Evaluation

Masato Yamamoto, Seiji Sakuraya, Yuji Kitsunai, Mark Kirk

Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A025, July 17–22, 2022

Paper No: PVP2022-82754

DOI: https://doi.org/10.1115/PVP2022-82754

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Topics: Reactor vessels, Steel, Temperature, Testing, Low temperature, Plasticity, Surveillance, ASTM International, Fracture toughness, Reliability

Proceedings Papers

State-of-the-Art of WPS in RPV PTS Analysis

Maksym Zarazovskii, Vladislav Pištora, Dana Lauerova, Florian Obermeier, Diego Fernando Mora Mendez, Yaroslav Dubyk, Tobias Bolinder, Carlos Cueto-Felgueroso Garcia, Szabolcs Szávai, Judit Dudra, Oriol Costa Garrido, Christophe Blain, Markku Puustinen, Jinya Katsuyama, B. Richard Bass, Paul T. Williams, Oleksii Shugailo

Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A083, July 17–22, 2022

Paper No: PVP2022-83699

DOI: https://doi.org/10.1115/PVP2022-83699

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Topics: Brittle fracture, Ductile fracture, Fracture (Materials), Fracture toughness, Heat, Reactor vessels, Steel, Stress, Thermal shock, Transients (Dynamics)

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

Development of a Technical Basis for Code Case N-914, “ Accounting for the Effect of Embrittlement on Fracture Toughness Properties Used in Evaluations of Pressure Boundary Materials in Class 1 Ferritic Steel Components, Section XI, Division 1 ”

Mark Kirk, Marjorie Erickson, Elliot J. Long

Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A045, July 17–22, 2022

Paper No: PVP2022-83909

DOI: https://doi.org/10.1115/PVP2022-83909

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Topics: Accounting, Embrittlement, Fracture toughness, Pressure, Reactor vessels, Steel

Proceedings Papers

Obtaining Low-Cost Estimates of the Master Curve Index Temperature T 0 From Existing Information

Mark Kirk, Naoki Miura, Tomoki Skinko, Masato Yamamoto

Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A044, July 17–22, 2022

Paper No: PVP2022-83905

DOI: https://doi.org/10.1115/PVP2022-83905

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Topics: Fracture toughness, Reactor vessels, Temperature, Testing, ASME Standards, Steel, Surveillance, Tension

Proceedings Papers

Development of Generic Unirradiated Values of T 0 and RT To for Use in ASME Code Applications

Marjorie Erickson, Mark Kirk, Elliot J. Long

Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A047, July 17–22, 2022

Paper No: PVP2022-84048

DOI: https://doi.org/10.1115/PVP2022-84048

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Topics: Accounting, ASME Standards, ASTM International, Embrittlement, Fracture toughness, Heat, Pressure, Reactor vessels, Steel, Temperature

Proceedings Papers

Validation of the Models in ASME CC N-830-1

Marjorie Erickson, Mark Kirk, Elliot J. Long

Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A046, July 17–22, 2022

Paper No: PVP2022-83921

DOI: https://doi.org/10.1115/PVP2022-83921

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Topics: ASME Standards, ASTM International, Flow (Dynamics), Fracture (Materials), Fracture toughness, Model validation, Reactor vessels, Steel, Temperature

Proceedings Papers

FRACTESUS Project: Final Selection of RPV Materials for Unirradiated and Irradiated Round Robins

Tomasz Brynk, Inge Uytdenhouwen, Pentti Arffman, Eberhard Altstadt, Radim Kopriva, Florian Obermeier, Marta Serrano

Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A026, July 17–22, 2022

Paper No: PVP2022-83871

DOI: https://doi.org/10.1115/PVP2022-83871

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Topics: Base metals, Databases, Fracture toughness, Irradiation (Radiation exposure), Mechanical properties, Neutrons, Notch testing, Reactor vessels, Temperature, Tension

Proceedings Papers

Study on Post-Buckling Behaviors of Lower Heads for Fracture Control of Reactor Vessels Under BDBE

Naoto Kasahara, Masato Murohara, Takuya Sato

Proc. ASME. PVP2022, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A037, July 17–22, 2022

Paper No: PVP2022-84449

DOI: https://doi.org/10.1115/PVP2022-84449

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Topics: Buckling, Fracture (Materials), Fracture (Process), Reactor vessels, Vessels

Proceedings Papers

Towards a Probabilistic Analysis of Pressurized Thermal Shock

C. D. Versteylen, N. B. Siccama, H. J. Uitslag-Doolaard, F. Brigante, E. Pallaoro, F. H. E. De Haan - De Wilde

Proc. ASME. PVP2022, Volume 3: Fluid-Structure Interaction; High Pressure Technology, V003T04A015, July 17–22, 2022

Paper No: PVP2022-84287

DOI: https://doi.org/10.1115/PVP2022-84287

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Topics: Thermal shock, Fracture (Materials), Stress, Reactor vessels, Computational fluid dynamics, Simulation, Brittleness, Fluids, Probability, Finite element methods

Proceedings Papers

Further Developments in Nuclear Pressure Vessel Manufacture Using the Hot Isostatic Pressing Process and Thick-Section Electron Beam Welding

Ted Warner, John Sulley, Phil Wallace, David Stewart, Gary Jones, Dan Thatcher

Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A004, July 17–22, 2022

Paper No: PVP2022-79403

DOI: https://doi.org/10.1115/PVP2022-79403

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Topics: Alloy steel, Cladding systems (Building), Electron beam welding, Hot pressing, Oxygen, Powder metallurgy, Pressure vessels, Reactor vessels

Proceedings Papers

BRUTE: Evaluation of Mechanical Properties of True Reactor Pressure Vessel Material From Barsebäck 2

Pentti Arffman, Jari Lydman, Noora Hytönen, Zaiqing Que, Sebastian Lindqvist

Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A034, July 17–22, 2022

Paper No: PVP2022-83819

DOI: https://doi.org/10.1115/PVP2022-83819

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Topics: Fracture (Materials), Fracture (Process), Mechanical properties, Reactor vessels

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

Effect of Welding Direction and Bead Pattern in Alloy 52 / SA508 Repair Weld

Heikki Keinänen, Juha Kuutti, Noora Hytönen, Pekka Nevasmaa, Caitlin Huotilainen, Iikka Virkkunen, Suprit Bhusare, Aloshious Lambai, Gaurav Mohanty

Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A053, July 17–22, 2022

Paper No: PVP2022-84662

DOI: https://doi.org/10.1115/PVP2022-84662

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Topics: Alloys, Gas metal arc welding, Indium alloys, Maintenance, Metals, Reactor vessels, Welding

Proceedings Papers

Determination of Irradiated Stainless Steel Properties and Its Effects on Reactor Vessel Internals

Dong-Hyeon Kwak, Jae Min Sim, Yoon-Suk Chang, Byeong Seo Kong, Changheui Jang

Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A049, July 17–22, 2022

Paper No: PVP2022-84936

DOI: https://doi.org/10.1115/PVP2022-84936

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Topics: Compression, Finite element analysis, Irradiation (Radiation exposure), Reactor vessels, Stainless steel, Dislocation density, Materials properties, Stress-strain curves, Boundary-value problems, Constitutive equations

Proceedings Papers

Round Robin Analysis of Small Punch Testing on 15Kh2NMFA Reference Material

Romy Welschen, Ferenc Gillemot, Igor Simonovski, Oliver Martin, Marek Adamech, Jana Petzova, Rebeca Hernandez, Radim Kopriva, Frederiki Naziris, Boy Molenaar, Murthy Kolluri

Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A046, July 17–22, 2022

Paper No: PVP2022-83811

DOI: https://doi.org/10.1115/PVP2022-83811

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Topics: Steel, Testing, Light water reactors, Manufacturing, Surveillance, Alloys, Brittleness, Creep, Disks, Fracture toughness

Proceedings Papers

Study on Ductile Crack Extension and Fracture Behavior in Plate Specimen With a Semi-Elliptical Surface Crack Using a BWR Reactor Pressure Vessel Material

Takahiro Hayashi, Takuya Ogawa, Shuichi Yoshida, Masao Itatani, Toshiyuki Saito

Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A020, July 17–22, 2022

Paper No: PVP2022-84606

DOI: https://doi.org/10.1115/PVP2022-84606

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Topics: Boiling water reactors, Ductile fracture, Fracture (Materials), Fracture (Process), Fracture mechanics, Metals, Reactor vessels, Stress corrosion cracking, Surface cracks

Proceedings Papers

Dedicated CT Tests and Numerical Simulations to Assess Crack Arrest by Quasi-Laminar Flaws

Pierre Dulieu, Valéry Lacroix, Robert Gérard, Tomasz Brynk, Inge Uytdenhouwen, Rachid Chaouadi

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A020, July 13–15, 2021

Paper No: PVP2021-60379

DOI: https://doi.org/10.1115/PVP2021-60379

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Topics: Computer simulation, Fracture (Materials), Fracture toughness, Reactor vessels, Stress, Accidents, Brittleness, Defense industry, Displacement, Engineering simulation

Proceedings Papers

Simplified Criteria With Reduced Testing Effort for Selecting Clad Materials for High Temperature Reactor Structural Components

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

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A037, July 13–15, 2021

Paper No: PVP2021-61858

DOI: https://doi.org/10.1115/PVP2021-61858

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Topics: High temperature, Structural elements (Construction), Testing, Creep, Design, Temperature, Alloys, Corrosion, Corrosion resistant materials, Design methodology

2 3 4 5

NARROW

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

Practical Procedure of Test Temperature Selection for Mini-C(T) Master Curve Evaluation

State-of-the-Art of WPS in RPV PTS Analysis

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

Development of a Technical Basis for Code Case N-914, “ Accounting for the Effect of Embrittlement on Fracture Toughness Properties Used in Evaluations of Pressure Boundary Materials in Class 1 Ferritic Steel Components, Section XI, Division 1 ”

Obtaining Low-Cost Estimates of the Master Curve Index Temperature T 0 From Existing Information

Development of Generic Unirradiated Values of T 0 and RT To for Use in ASME Code Applications

Validation of the Models in ASME CC N-830-1

FRACTESUS Project: Final Selection of RPV Materials for Unirradiated and Irradiated Round Robins

Study on Post-Buckling Behaviors of Lower Heads for Fracture Control of Reactor Vessels Under BDBE

Towards a Probabilistic Analysis of Pressurized Thermal Shock

Further Developments in Nuclear Pressure Vessel Manufacture Using the Hot Isostatic Pressing Process and Thick-Section Electron Beam Welding

BRUTE: Evaluation of Mechanical Properties of True Reactor Pressure Vessel Material From Barsebäck 2

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

Effect of Welding Direction and Bead Pattern in Alloy 52 / SA508 Repair Weld

Determination of Irradiated Stainless Steel Properties and Its Effects on Reactor Vessel Internals

Round Robin Analysis of Small Punch Testing on 15Kh2NMFA Reference Material

Study on Ductile Crack Extension and Fracture Behavior in Plate Specimen With a Semi-Elliptical Surface Crack Using a BWR Reactor Pressure Vessel Material

Dedicated CT Tests and Numerical Simulations to Assess Crack Arrest by Quasi-Laminar Flaws

Simplified Criteria With Reduced Testing Effort for Selecting Clad Materials for High Temperature Reactor Structural Components

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