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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

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

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

Fracture Analysis of Reactor Pressure Vessel Lower Head Considering Core Meltdown Accident

Yaroslav Dubyk, Vitalii Antonchenko, Maksym Zarazovskii

Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A063, July 13–15, 2021

Paper No: PVP2021-62062

DOI: https://doi.org/10.1115/PVP2021-62062

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Topics: Accidents, Fracture (Materials), Reactor vessels, Vessels, Boundary-value problems, Cavities, Cooling, Creep, Floods, Fracture mechanics

Proceedings Papers

Crack Propagation Calculation for Axial Cracks in Hollow Cylinders Subjected to Thermal Shock

Diego F. Mora M., Markus Niffenegger

Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A044, July 13–15, 2021

Paper No: PVP2021-61406

DOI: https://doi.org/10.1115/PVP2021-61406

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Topics: Algorithms, Crack propagation, Cylinders, Fracture (Materials), Stress, Thermal shock, Weight (Mass)

Proceedings Papers

Pressurized Thermal Shock Analysis With Sub-Modeling

L. Stefanini, C. Versteylen, F. S. L. Pangukir, H. J. Uitslag-Doolaard, F. H. E. de Haan - de Wilde

Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T05A014, July 13–15, 2021

Paper No: PVP2021-61794

DOI: https://doi.org/10.1115/PVP2021-61794

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Topics: Computational fluid dynamics, Modeling, Thermal shock

Proceedings Papers

Progress of EASICS Validation Experiments and Code Comparison of R5, RCC-MRX and ASME III Division V

Peter James, David Coon, Colin Austin, Nicholas Underwood, Caroline Meek, Marc Chevalier, David Dean

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A031, July 13–15, 2021

Paper No: PVP2021-62845

DOI: https://doi.org/10.1115/PVP2021-62845

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Topics: Compression, Creep, Design, Displacement, Engineering standards, Fatigue, Fatigue testing, Generation IV reactors, High temperature, Pipes

Proceedings Papers

Investigation Into Residual Stresses in a Small Bore Pipe Weld With Stacked Stop/Start Locations

Ben Pellereau, Simon Walter, Paul Pembury

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A113, August 3, 2020

Paper No: PVP2020-21629

DOI: https://doi.org/10.1115/PVP2020-21629

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Topics: Pipes, Residual stresses, Stress, Fatigue, Fatigue cracks, Finite element model, Fracture (Materials), Fracture (Process), Gas tungsten arc welding, Membranes

Proceedings Papers

Constraint Effect on Fracture Mechanics Evaluation for an Under-Clad Crack in a Reactor Pressure Vessel Steel

Masaki Shimodaira, Tohru Tobita, Hisashi Takamizawa, Jinya Katsuyama, Satoshi Hanawa

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A049, August 3, 2020

Paper No: PVP2020-21441

DOI: https://doi.org/10.1115/PVP2020-21441

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Topics: Finite element analysis, Fracture (Materials), Fracture mechanics, Fracture toughness, Reactor vessels, Steel, Surface cracks, Cladding systems (Building), Stress, Anisotropy

Proceedings Papers

Extension of PASCAL4 Code for Probabilistic Fracture Mechanics Analysis of Reactor Pressure Vessel in Boiling Water Reactor

Kai Lu, Jinya Katsuyama, Yinsheng Li

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A062, August 3, 2020

Paper No: PVP2020-21421

DOI: https://doi.org/10.1115/PVP2020-21421

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Topics: Boiling water reactors, Fracture mechanics, Reactor vessels, Transients (Dynamics), Fracture (Materials), Pressurized water reactors, Surface cracks, Computational methods, Embrittlement, Irradiation (Radiation exposure)

Proceedings Papers

Overview of EASICS Validation Experiments and Code Comparison of R5, RCC-MRX and ASME III Division V

Peter James, David Coon, Colin Austin, Nicholas Underwood, Marc Chevalier, David Dean

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A093, August 3, 2020

Paper No: PVP2020-21720

DOI: https://doi.org/10.1115/PVP2020-21720

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Topics: Compression, Creep, Design, Displacement, Engineering standards, Fatigue, Fatigue testing, Generation IV reactors, High temperature, Sodium

Proceedings Papers

Evaluation of Susceptibility to Thermal Fatigue Cracking in High Temperature Alloys for Refinery Olefin Applications

Yuxiang Zhang, Ryan Buntain, Jacob Edwards, Boian Alexandrov, Jorge A. Penso

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A059, August 3, 2020

Paper No: PVP2020-21741

DOI: https://doi.org/10.1115/PVP2020-21741

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Topics: Alloys, Fatigue, Fatigue cracks, Fracture (Materials), High temperature, Thermomechanics, Gages, Cycles, Fracture (Process), Furnaces

Proceedings Papers

Consideration of Special Effects for the Application of an Optimized Fracture Mechanics Approach for the RPV Assessment: Project CAMERA

Florian Obermeier, Hieronymus Hein, Johannes May, Julia Kobiela, Marco Kaiser

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A044, August 3, 2020

Paper No: PVP2020-21464

DOI: https://doi.org/10.1115/PVP2020-21464

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Topics: ASTM International, Brittleness, Databases, Fracture (Materials), Fracture mechanics, Fracture toughness, Metals, Operating temperature, Pressurized water reactors, Reactor vessels

Proceedings Papers

Fatigue Initiation of 304L Stainless Steel Subject to Thermal Shock Loading in a PWR Environment

Peter Gill, Peter Brown, David Tice, Norman Platts, Chris Currie

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A023, July 14–19, 2019

Paper No: PVP2019-93923

DOI: https://doi.org/10.1115/PVP2019-93923

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Topics: Fatigue, Pressurized water reactors, Stainless steel, Thermal shock, Cycles, Temperature, Transients (Dynamics), Stress, Testing, Design

Proceedings Papers

Application of Probabilistic Fracture Mechanics Methodology for Japanese Reactor Pressure Vessels Using PASCAL4

Kai Lu, Jinya Katsuyama, Yinsheng Li, Shinobu Yoshimura

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A057, July 14–19, 2019

Paper No: PVP2019-93935

DOI: https://doi.org/10.1115/PVP2019-93935

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Topics: Fracture mechanics, Reactor vessels, Failure, Neutrons, Embrittlement, Fluence (Radiation measurement), Irradiation (Radiation exposure), Light water reactors, Nondestructive evaluation, Nuclear power

Proceedings Papers

PTS Evaluation Case Study Considering Actual Through-Wall Fracture Toughness Distribution

Masato Yamamoto, Masaki Nagai

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A037, July 14–19, 2019

Paper No: PVP2019-93964

DOI: https://doi.org/10.1115/PVP2019-93964

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Topics: Fracture toughness, Base metals, Fracture (Materials), Belts, Fluence (Radiation measurement), Fracture mechanics, Neutrons, Nuclear research, Probability, Surveillance

Proceedings Papers

Effect of Coolant Water Temperature of ECCS on Failure Probability of RPV

Jinya Katsuyama, Koichi Masaki, Kai Lu, Tadashi Watanabe, Yinsheng Li

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A059, July 14–19, 2019

Paper No: PVP2019-93967

DOI: https://doi.org/10.1115/PVP2019-93967

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Topics: Coolants, Emergency core cooling systems, Failure, Fracture mechanics, Probability, Thermal shock, Water temperature, Temperature, Pressure, Pressurized water reactors

Proceedings Papers

Critical Review of Strain Measures for Characterisation of Fatigue Damage in ASME Section III Fatigue Assessments

Daniel Leary, Chris Currie, Keith Wright

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A020, July 14–19, 2019

Paper No: PVP2019-93849

DOI: https://doi.org/10.1115/PVP2019-93849

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Topics: Fatigue, Fatigue damage, Stress, ASME Standards, Pipes, Design, Fracture (Materials), Plane strain, Pressure vessel construction, Reactor vessels

Proceedings Papers

Comparison and Assessment of the Creep-Fatigue and Ratcheting Design Methods for a Reference Gen3 Molten Salt Concentrated Solar Power Receiver

B. Barua, M. C. Messner, M. D. McMurtrey

Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A100, July 14–19, 2019

Paper No: PVP2019-93572

DOI: https://doi.org/10.1115/PVP2019-93572

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Topics: Concentrating solar power, Creep, Design methodology, Fatigue, Design, Temperature, Thermodynamic power cycles, ASME Boiler and Pressure Vessel Code, Brayton cycle, Constitutive equations

Proceedings Papers

Uncertainties in Pressurized Thermal Shock Analyses

M. Niffenegger, O. Costa Garrido, D. F. Mora, G. Qian, R. Mukin, M. Sharabi, N. Lafferty, B. Niceno

Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A101, July 14–19, 2019

Paper No: PVP2019-94076

DOI: https://doi.org/10.1115/PVP2019-94076

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Topics: Computational fluid dynamics, Fracture mechanics, Thermal shock, Uncertainty

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NARROW

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

Towards a Probabilistic Analysis of Pressurized Thermal Shock

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

Fracture Analysis of Reactor Pressure Vessel Lower Head Considering Core Meltdown Accident

Crack Propagation Calculation for Axial Cracks in Hollow Cylinders Subjected to Thermal Shock

Pressurized Thermal Shock Analysis With Sub-Modeling

Progress of EASICS Validation Experiments and Code Comparison of R5, RCC-MRX and ASME III Division V

Investigation Into Residual Stresses in a Small Bore Pipe Weld With Stacked Stop/Start Locations

Constraint Effect on Fracture Mechanics Evaluation for an Under-Clad Crack in a Reactor Pressure Vessel Steel

Extension of PASCAL4 Code for Probabilistic Fracture Mechanics Analysis of Reactor Pressure Vessel in Boiling Water Reactor

Overview of EASICS Validation Experiments and Code Comparison of R5, RCC-MRX and ASME III Division V

Evaluation of Susceptibility to Thermal Fatigue Cracking in High Temperature Alloys for Refinery Olefin Applications

Consideration of Special Effects for the Application of an Optimized Fracture Mechanics Approach for the RPV Assessment: Project CAMERA

Fatigue Initiation of 304L Stainless Steel Subject to Thermal Shock Loading in a PWR Environment

Application of Probabilistic Fracture Mechanics Methodology for Japanese Reactor Pressure Vessels Using PASCAL4

PTS Evaluation Case Study Considering Actual Through-Wall Fracture Toughness Distribution

Effect of Coolant Water Temperature of ECCS on Failure Probability of RPV

Critical Review of Strain Measures for Characterisation of Fatigue Damage in ASME Section III Fatigue Assessments

Comparison and Assessment of the Creep-Fatigue and Ratcheting Design Methods for a Reference Gen3 Molten Salt Concentrated Solar Power Receiver

Uncertainties in Pressurized Thermal Shock Analyses

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