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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
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 ”
Click here to open pdf in another window PDF for 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 ”
Topics: Accounting, Embrittlement, Fracture toughness, Pressure, Reactor vessels, Steel
Proceedings Papers

Use of Mini-CT Specimens for Fracture Toughness Characterization of Irradiated Highly Embrittled Weld

Mikhail A. Sokolov
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A027, July 17–22, 2022
Paper No: PVP2022-84827
DOI: https://doi.org/10.1115/PVP2022-84827
View Paper titled, Use of Mini-CT Specimens for Fracture Toughness Characterization of Irradiated Highly Embrittled Weld
Click here to open pdf in another window PDF for Use of Mini-CT Specimens for Fracture Toughness Characterization of Irradiated Highly Embrittled Weld
Topics: Embrittlement, Fracture toughness, Radiation (Physics)
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
View Paper titled, Development of Generic Unirradiated Values of T 0 and RT To for Use in ASME Code Applications
Click here to open pdf in another window PDF for Development of Generic Unirradiated Values of T 0 and RT To for Use in ASME Code Applications
Topics: Accounting, ASME Standards, ASTM International, Embrittlement, Fracture toughness, Heat, Pressure, Reactor vessels, Steel, Temperature
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

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

Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys

Xiang (Frank) Chen, Kevin G. Field, Richard Howard, Caleb P. Massey, Andrew T. Nelson
Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A019, July 17–22, 2022
Paper No: PVP2022-84517
DOI: https://doi.org/10.1115/PVP2022-84517
View Paper titled, Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys
Click here to open pdf in another window PDF for Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys
Topics: Accidents, Alloys, Cladding systems (Building), Embrittlement, Fracture toughness, Fuels, Hardening, Irradiation (Radiation exposure)
Proceedings Papers

A Methodology for Calculating the Minimum Pressurization Temperature of New Built Hydroprocessing Reactors in 2¼Cr-1Mo-¼V Low Alloy Steel

Jan-Willem Rensman, Davide Frittitta, Fausto Fusari, Nicola Ronchi
Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A011, July 17–22, 2022
Paper No: PVP2022-84640
DOI: https://doi.org/10.1115/PVP2022-84640
View Paper titled, A Methodology for Calculating the Minimum Pressurization Temperature of New Built Hydroprocessing Reactors in 2¼Cr-1Mo-¼V Low Alloy Steel
Click here to open pdf in another window PDF for A Methodology for Calculating the Minimum Pressurization Temperature of New Built Hydroprocessing Reactors in 2¼Cr-1Mo-¼V Low Alloy Steel
Topics: Alloy steel, Embrittlement, Hydrogen embrittlement, Temperature
Proceedings Papers

DetaClad™ Characterization for High-Temperature and High-Pressure Hydrogen Service

Olivier Sarrat, Curtis Prothe, Tim Delahanty
Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A022, July 17–22, 2022
Paper No: PVP2022-80639
DOI: https://doi.org/10.1115/PVP2022-80639
View Paper titled, DetaClad™ Characterization for High-Temperature and High-Pressure Hydrogen Service
Click here to open pdf in another window PDF for DetaClad™ Characterization for High-Temperature and High-Pressure Hydrogen Service
Topics: Corrosion, High pressure (Physics), High temperature, Hydrogen, Cladding systems (Building), Pressure vessels, Alloys, Bond strength, Carbon steel, Damage
Proceedings Papers

Finite Element Analysis of Ring Compression Testing for Used Nuclear Fuel Cladding

Zenghu Han, Michael C. Billone, Yung Y. Liu
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A024, July 17–22, 2022
Paper No: PVP2022-83911
DOI: https://doi.org/10.1115/PVP2022-83911
View Paper titled, Finite Element Analysis of Ring Compression Testing for Used Nuclear Fuel Cladding
Click here to open pdf in another window PDF for Finite Element Analysis of Ring Compression Testing for Used Nuclear Fuel Cladding
Topics: Cladding systems (Building), Compression, Finite element analysis, Nuclear fuels, Testing, Storage, Transportation systems, Ductility, Fuels, Mechanical properties
Proceedings Papers

Regression Analysis of Transition Temperature Shift Database for the Core Region Beltline Welds of WWER-1000 RPVs

Maksym Zarazovskii, Volodymyr Revka, Liudmyla Chyrko
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A018, August 3, 2020
Paper No: PVP2020-21748
DOI: https://doi.org/10.1115/PVP2020-21748
View Paper titled, Regression Analysis of Transition Temperature Shift Database for the Core Region Beltline Welds of WWER-1000 RPVs
Click here to open pdf in another window PDF for Regression Analysis of Transition Temperature Shift Database for the Core Region Beltline Welds of WWER-1000 RPVs
Topics: Brittleness, Databases, Embrittlement, Phase transition temperature, Radiation (Physics), Regression analysis, Surveillance, Temperature, Welded joints, Silicon
Proceedings Papers

Cracking Behavior of a Decommissioned Material in Light Water Reactor Environment

Y. Chen, B. Alexandreanu, A. S. Rao
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A071, August 3, 2020
Paper No: PVP2020-21141
DOI: https://doi.org/10.1115/PVP2020-21141
View Paper titled, Cracking Behavior of a Decommissioned Material in Light Water Reactor Environment
Click here to open pdf in another window PDF for Cracking Behavior of a Decommissioned Material in Light Water Reactor Environment
Topics: Embrittlement, Fracture (Materials), Fracture (Process), Fracture toughness, Irradiation (Radiation exposure), Light water reactors, Stress corrosion cracking
Proceedings Papers

Fracture Toughness Tests on Western RPV Steels Using Small Scale Specimen Technique

Florian Obermeier, Eberhard Altstadt, Hieronymus Hein, Aniruddh Das
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A102, August 3, 2020
Paper No: PVP2020-21481
DOI: https://doi.org/10.1115/PVP2020-21481
View Paper titled, Fracture Toughness Tests on Western RPV Steels Using Small Scale Specimen Technique
Click here to open pdf in another window PDF for Fracture Toughness Tests on Western RPV Steels Using Small Scale Specimen Technique
Topics: Embrittlement, Fracture mechanics, Fracture toughness, Irradiation (Radiation exposure), Reactor vessels, Steel, Surveillance, Displacement, Brittle fracture, Cracking (Materials)
Proceedings Papers

Effect of Hydrogen Content in Natural Gas Blend on the Mechanical Properties of a L485-MB Low-Alloyed Steel

Hamza Ez-Zaki, Frederic Christien, Cédric Bosch, Laurent Briottet, Maxime Bertin, Olivier Levasseur, Alain Leriverain
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A085, August 3, 2020
Paper No: PVP2020-21228
DOI: https://doi.org/10.1115/PVP2020-21228
View Paper titled, Effect of Hydrogen Content in Natural Gas Blend on the Mechanical Properties of a L485-MB Low-Alloyed Steel
Click here to open pdf in another window PDF for Effect of Hydrogen Content in Natural Gas Blend on the Mechanical Properties of a L485-MB Low-Alloyed Steel
Topics: Alloy steel, Hydrogen, Mechanical properties, Natural gas, Steel, Pressure, Fracture (Materials), Fracture (Process), Testing, Ductility
Proceedings Papers

A Code Case Concerning the Effect of Embrittlement on Index Temperature Metrics

Mark Kirk, Marjorie Erickson
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A056, August 3, 2020
Paper No: PVP2020-21185
DOI: https://doi.org/10.1115/PVP2020-21185
View Paper titled, A Code Case Concerning the Effect of Embrittlement on Index Temperature Metrics
Click here to open pdf in another window PDF for A Code Case Concerning the Effect of Embrittlement on Index Temperature Metrics
Topics: Embrittlement, Temperature, Accounting, Fracture toughness, Nuclear power stations, Safety, Uncertainty
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

Bayesian Uncertainty Evaluation of Charpy Ductile-to-Brittle Transition Temperature for Reactor Pressure Vessel Steels

Hisashi Takamizawa, Yutaka Nishiyama, Takashi Hirano
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A065, August 3, 2020
Paper No: PVP2020-21698
DOI: https://doi.org/10.1115/PVP2020-21698
View Paper titled, Bayesian Uncertainty Evaluation of Charpy Ductile-to-Brittle Transition Temperature for Reactor Pressure Vessel Steels
Click here to open pdf in another window PDF for Bayesian Uncertainty Evaluation of Charpy Ductile-to-Brittle Transition Temperature for Reactor Pressure Vessel Steels
Topics: Brittleness, Embrittlement, Irradiation (Radiation exposure), Notch testing, Phase transition temperature, Reactor vessels, Statistics, Steel, Uncertainty
Proceedings Papers

Coupling of Neutron Transport and Probabilistic Fracture Mechanics Codes for Analysis of Embrittled Reactor Pressure Vessels

Benjamin W. Spencer, William M. Hoffman, Benjamin S. Collins, Shane C. Henderson
Proc. ASME. PVP2020, Volume 3: Design and Analysis, V003T03A057, August 3, 2020
Paper No: PVP2020-21680
DOI: https://doi.org/10.1115/PVP2020-21680
View Paper titled, Coupling of Neutron Transport and Probabilistic Fracture Mechanics Codes for Analysis of Embrittled Reactor Pressure Vessels
Click here to open pdf in another window PDF for Coupling of Neutron Transport and Probabilistic Fracture Mechanics Codes for Analysis of Embrittled Reactor Pressure Vessels
Topics: Embrittlement, Fluence (Radiation measurement), Fracture mechanics, Neutrons, Reactor vessels
Proceedings Papers

Non-Destructive Evaluation of RPV Embrittlement by Means of the Thermoelectric Power Method

M. Niffenegger, D. F. Mora, H. Kottmann
Proc. ASME. PVP2020, Volume 7: Non-Destructive Examination, V007T07A002, August 3, 2020
Paper No: PVP2020-21446
DOI: https://doi.org/10.1115/PVP2020-21446
View Paper titled, Non-Destructive Evaluation of RPV Embrittlement by Means of the Thermoelectric Power Method
Click here to open pdf in another window PDF for Non-Destructive Evaluation of RPV Embrittlement by Means of the Thermoelectric Power Method
Topics: Embrittlement, Nondestructive evaluation, Steel
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

Recent Improvements in Toughness Prediction of Cast Duplex Stainless Steel Components

Patrick Le Delliou, Sébastien Saillet
Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A050, July 14–19, 2019
Paper No: PVP2019-93114
DOI: https://doi.org/10.1115/PVP2019-93114
View Paper titled, Recent Improvements in Toughness Prediction of Cast Duplex Stainless Steel Components
Click here to open pdf in another window PDF for Recent Improvements in Toughness Prediction of Cast Duplex Stainless Steel Components
Topics: Fracture toughness, Stainless steel, Notch testing, Steel, Temperature, Casting, Cavities, Crack propagation, Embrittlement, Ferrites (Magnetic materials)