1-20 of 190
Thermal shock
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
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
View Paper titled, State-of-the-Art of WPS in RPV PTS Analysis
Click here to open pdf in another window PDF for State-of-the-Art of WPS in RPV PTS Analysis
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
View Paper titled, Towards a Probabilistic Analysis of Pressurized Thermal Shock
Click here to open pdf in another window PDF for Towards a Probabilistic Analysis of Pressurized Thermal Shock
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
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

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
View Paper titled, Progress of EASICS Validation Experiments and Code Comparison of R5, RCC-MRX and ASME III Division V
Click here to open pdf in another window PDF for Progress of EASICS Validation Experiments and Code Comparison of R5, RCC-MRX and ASME III Division V
Topics: Compression, Creep, Design, Displacement, Engineering standards, Fatigue, Fatigue testing, Generation IV reactors, High temperature, Pipes
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
View Paper titled, Fracture Analysis of Reactor Pressure Vessel Lower Head Considering Core Meltdown Accident
Click here to open pdf in another window PDF for Fracture Analysis of Reactor Pressure Vessel Lower Head Considering Core Meltdown Accident
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
View Paper titled, Crack Propagation Calculation for Axial Cracks in Hollow Cylinders Subjected to Thermal Shock
Click here to open pdf in another window PDF for Crack Propagation Calculation for Axial Cracks in Hollow Cylinders Subjected to Thermal Shock
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
View Paper titled, Pressurized Thermal Shock Analysis With Sub-Modeling
Click here to open pdf in another window PDF for Pressurized Thermal Shock Analysis With Sub-Modeling
Topics: Computational fluid dynamics, Modeling, Thermal shock
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
View Paper titled, Consideration of Special Effects for the Application of an Optimized Fracture Mechanics Approach for the RPV Assessment: Project CAMERA
Click here to open pdf in another window PDF for Consideration of Special Effects for the Application of an Optimized Fracture Mechanics Approach for the RPV Assessment: Project CAMERA
Topics: ASTM International, Brittleness, Databases, Fracture (Materials), Fracture mechanics, Fracture toughness, Metals, Operating temperature, Pressurized water reactors, Reactor vessels
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
View Paper titled, Evaluation of Susceptibility to Thermal Fatigue Cracking in High Temperature Alloys for Refinery Olefin Applications
Click here to open pdf in another window PDF for Evaluation of Susceptibility to Thermal Fatigue Cracking in High Temperature Alloys for Refinery Olefin Applications
Topics: Alloys, Fatigue, Fatigue cracks, Fracture (Materials), High temperature, Thermomechanics, Gages, Cycles, Fracture (Process), Furnaces
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
View Paper titled, Investigation Into Residual Stresses in a Small Bore Pipe Weld With Stacked Stop/Start Locations
Click here to open pdf in another window PDF for Investigation Into Residual Stresses in a Small Bore Pipe Weld With Stacked Stop/Start Locations
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
View Paper titled, Constraint Effect on Fracture Mechanics Evaluation for an Under-Clad Crack in a Reactor Pressure Vessel Steel
Click here to open pdf in another window PDF for Constraint Effect on Fracture Mechanics Evaluation for an Under-Clad Crack in a Reactor Pressure Vessel Steel
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
View Paper titled, Extension of PASCAL4 Code for Probabilistic Fracture Mechanics Analysis of Reactor Pressure Vessel in Boiling Water Reactor
Click here to open pdf in another window PDF for Extension of PASCAL4 Code for Probabilistic Fracture Mechanics Analysis of Reactor Pressure Vessel in Boiling Water Reactor
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
View Paper titled, Overview of EASICS Validation Experiments and Code Comparison of R5, RCC-MRX and ASME III Division V
Click here to open pdf in another window PDF for Overview of EASICS Validation Experiments and Code Comparison of R5, RCC-MRX and ASME III Division V
Topics: Compression, Creep, Design, Displacement, Engineering standards, Fatigue, Fatigue testing, Generation IV reactors, High temperature, Sodium
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
View Paper titled, Fatigue Initiation of 304L Stainless Steel Subject to Thermal Shock Loading in a PWR Environment
Click here to open pdf in another window PDF for Fatigue Initiation of 304L Stainless Steel Subject to Thermal Shock Loading in a PWR Environment
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
View Paper titled, Application of Probabilistic Fracture Mechanics Methodology for Japanese Reactor Pressure Vessels Using PASCAL4
Click here to open pdf in another window PDF for Application of Probabilistic Fracture Mechanics Methodology for Japanese Reactor Pressure Vessels Using PASCAL4
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
View Paper titled, PTS Evaluation Case Study Considering Actual Through-Wall Fracture Toughness Distribution
Click here to open pdf in another window PDF for PTS Evaluation Case Study Considering Actual Through-Wall Fracture Toughness Distribution
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
View Paper titled, Effect of Coolant Water Temperature of ECCS on Failure Probability of RPV
Click here to open pdf in another window PDF for Effect of Coolant Water Temperature of ECCS on Failure Probability of RPV
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
View Paper titled, Critical Review of Strain Measures for Characterisation of Fatigue Damage in ASME Section III Fatigue Assessments
Click here to open pdf in another window PDF for Critical Review of Strain Measures for Characterisation of Fatigue Damage in ASME Section III Fatigue Assessments
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
View Paper titled, Comparison and Assessment of the Creep-Fatigue and Ratcheting Design Methods for a Reference Gen3 Molten Salt Concentrated Solar Power Receiver
Click here to open pdf in another window PDF for Comparison and Assessment of the Creep-Fatigue and Ratcheting Design Methods for a Reference Gen3 Molten Salt Concentrated Solar Power Receiver
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
View Paper titled, Uncertainties in Pressurized Thermal Shock Analyses
Click here to open pdf in another window PDF for Uncertainties in Pressurized Thermal Shock Analyses
Topics: Computational fluid dynamics, Fracture mechanics, Thermal shock, Uncertainty