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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
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
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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
https://doi.org/10.1115/PVP2022-82754
View Paper titled, Practical Procedure of Test Temperature Selection for Mini-C(T) Master Curve Evaluation
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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
https://doi.org/10.1115/PVP2022-83699
View Paper titled, State-of-the-Art of WPS in RPV PTS Analysis
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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
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
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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
https://doi.org/10.1115/PVP2022-83909
View Paper titled, 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 ”
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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
https://doi.org/10.1115/PVP2022-83905
View Paper titled, Obtaining Low-Cost Estimates of the Master Curve Index Temperature T 0 From Existing Information
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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
https://doi.org/10.1115/PVP2022-84048
View Paper titled, Development of Generic Unirradiated Values of T 0 and RT To for Use in ASME Code Applications
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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
https://doi.org/10.1115/PVP2022-83921
View Paper titled, Validation of the Models in ASME CC N-830-1
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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
https://doi.org/10.1115/PVP2022-83871
View Paper titled, FRACTESUS Project: Final Selection of RPV Materials for Unirradiated and Irradiated Round Robins
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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
https://doi.org/10.1115/PVP2022-84449
View Paper titled, Study on Post-Buckling Behaviors of Lower Heads for Fracture Control of Reactor Vessels Under BDBE
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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
https://doi.org/10.1115/PVP2022-84287
View Paper titled, Towards a Probabilistic Analysis of Pressurized Thermal Shock
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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
https://doi.org/10.1115/PVP2022-79403
View Paper titled, Further Developments in Nuclear Pressure Vessel Manufacture Using the Hot Isostatic Pressing Process and Thick-Section Electron Beam Welding
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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
https://doi.org/10.1115/PVP2022-83819
View Paper titled, BRUTE: Evaluation of Mechanical Properties of True Reactor Pressure Vessel Material From Barsebäck 2
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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
https://doi.org/10.1115/PVP2022-80693
View Paper titled, Advanced Structural Integrity Assessment Tools for Safe Long Term Operation (ATLAS+)
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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
https://doi.org/10.1115/PVP2022-84662
View Paper titled, Effect of Welding Direction and Bead Pattern in Alloy 52 / SA508 Repair Weld
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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
https://doi.org/10.1115/PVP2022-84936
View Paper titled, Determination of Irradiated Stainless Steel Properties and Its Effects on Reactor Vessel Internals
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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
https://doi.org/10.1115/PVP2022-83811
View Paper titled, Round Robin Analysis of Small Punch Testing on 15Kh2NMFA Reference Material
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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
https://doi.org/10.1115/PVP2022-84606
View Paper titled, Study on Ductile Crack Extension and Fracture Behavior in Plate Specimen With a Semi-Elliptical Surface Crack Using a BWR Reactor Pressure Vessel Material
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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

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

Study on Fracture Behavior and Assessment for Dissimilar Metal Weld of Low Alloy Steel and Ni-Base Alloy Weld Using a BWR Reactor Pressure Vessel Material

Takahiro Hayashi, Takuya Ogawa, Shuichi Yoshida, Masao Itatani, Yasuhiro Hattori, Tetsushi Yamaoka, Shigeaki Tanaka, Toshiyuki Saito
Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A047, July 13–15, 2021
Paper No: PVP2021-61467
https://doi.org/10.1115/PVP2021-61467
View Paper titled, Study on Fracture Behavior and Assessment for Dissimilar Metal Weld of Low Alloy Steel and Ni-Base Alloy Weld Using a BWR Reactor Pressure Vessel Material
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Topics: Alloy steel, Alloys, Boiling water reactors, Fracture (Materials), Fracture mechanics, Fracture toughness, Metals, Reactor vessels, Stress corrosion cracking