1-20 of 216
Embrittlement
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

Master Curve Evaluation Using Miniature C(T) Specimens as Part of a Round Robin Program Within the FRACTESUS Project

Frideriki Naziris, Rebeca Hernandez Pascual, Timo Metzler, Ermile Gaganidze, Inge Uytdenhouwen, Murthy Kolluri
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A045, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-107254
https://doi.org/10.1115/PVP2023-107254
View Paper titled, Master Curve Evaluation Using Miniature C(T) Specimens as Part of a Round Robin Program Within the FRACTESUS Project
Open the PDF for Master Curve Evaluation Using Miniature C(T) Specimens as Part of a Round Robin Program Within the FRACTESUS Project in another window
Topics: ASTM International, Design, Embrittlement, Fluence (Radiation measurement), Fracture toughness, Geometry, Machinery, Machining, Manipulators, Reactor vessels
Proceedings Papers

Assessment of the Need to Consider HAZ Properties as Part of RPV Integrity Management

Mark Kirk, Marjorie Erickson, Elliot J. Long
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A033, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105904
https://doi.org/10.1115/PVP2023-105904
View Paper titled, Assessment of the Need to Consider HAZ Properties as Part of RPV Integrity Management
Open the PDF for Assessment of the Need to Consider HAZ Properties as Part of RPV Integrity Management in another window
Topics: ASME Standards, Base metals, Electromagnetic scattering, Embrittlement, Fracture toughness, Heat, Irradiation (Radiation exposure), Metals, Neutrons, Phase transition temperature
Proceedings Papers

Fractography of Neutron Irradiated RPV Steels – A Comparison of Shift in Reference Temperature and Net Hardening

Aniruddh Das, Paul Chekhonin, Mario Houska, Florian Obermeier, Eberhard Altstadt
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A028, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-103648
https://doi.org/10.1115/PVP2023-103648
View Paper titled, Fractography of Neutron Irradiated RPV Steels – A Comparison of Shift in Reference Temperature and Net Hardening
Open the PDF for Fractography of Neutron Irradiated RPV Steels – A Comparison of Shift in Reference Temperature and Net Hardening in another window
Topics: Fractography, Hardening, Neutrons, Steel, Temperature, Fracture (Materials), Irradiation (Radiation exposure), Embrittlement, Fracture toughness, Yield strength
Proceedings Papers

Comprehensive Modelling of Pressurized Thermal Shock With a Probabilistic Approach

Fabio Pasti, Sina Tajfirooz, H. J. Uitslag-Doolaard, Francesco Brigante, F. H. E. De Haan-De Wilde
Proc. ASME. PVP2023, Volume 3: Fluid-Structure Interaction, V003T04A029, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105923
https://doi.org/10.1115/PVP2023-105923
View Paper titled, Comprehensive Modelling of Pressurized Thermal Shock With a Probabilistic Approach
Open the PDF for Comprehensive Modelling of Pressurized Thermal Shock With a Probabilistic Approach in another window
Topics: Computational fluid dynamics, Finite element methods, Fracture (Materials), Modeling, Thermal shock, Fracture (Process), Fluids, Simulation, Stress, Brittleness
Proceedings Papers

Comprehensive Prediction for Temper Embrittlement of Hydrogenation Reactors in Long-Term Service Condition

Juanbo Liu, Zhiyuan Han, Haoyuan Kang, Sheng Chen, Libin Song, Meng He
Proc. ASME. PVP2023, Volume 5: Materials & Fabrication, V005T06A043, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105977
https://doi.org/10.1115/PVP2023-105977
View Paper titled, Comprehensive Prediction for Temper Embrittlement of Hydrogenation Reactors in Long-Term Service Condition
Open the PDF for Comprehensive Prediction for Temper Embrittlement of Hydrogenation Reactors in Long-Term Service Condition in another window
Topics: Embrittlement
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84287
https://doi.org/10.1115/PVP2022-84287
View Paper titled, Towards a Probabilistic Analysis of Pressurized Thermal Shock
Open the PDF for Towards a Probabilistic Analysis of Pressurized Thermal Shock in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-85520
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
Open the PDF for Impact of Thermal Ageing Embrittlement on Westinghouse and Combustion Engineering-Designed Pressurized Water Reactor Pressurizers Based on Pressure-Temperature Limit Comparison in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84517
https://doi.org/10.1115/PVP2022-84517
View Paper titled, Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys
Open the PDF for Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84640
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
Open the PDF for A Methodology for Calculating the Minimum Pressurization Temperature of New Built Hydroprocessing Reactors in 2¼Cr-1Mo-¼V Low Alloy Steel in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-80639
https://doi.org/10.1115/PVP2022-80639
View Paper titled, DetaClad™ Characterization for High-Temperature and High-Pressure Hydrogen Service
Open the PDF for DetaClad™ Characterization for High-Temperature and High-Pressure Hydrogen Service in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-83911
https://doi.org/10.1115/PVP2022-83911
View Paper titled, Finite Element Analysis of Ring Compression Testing for Used Nuclear Fuel Cladding
Open the PDF for Finite Element Analysis of Ring Compression Testing for Used Nuclear Fuel Cladding in another window
Topics: Cladding systems (Building), Compression, Finite element analysis, Nuclear fuels, Testing, Storage, Transportation systems, Ductility, Fuels, Mechanical properties
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
Publisher: American Society of Mechanical Engineers
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 ”
Open the 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 ” in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84827
https://doi.org/10.1115/PVP2022-84827
View Paper titled, Use of Mini-CT Specimens for Fracture Toughness Characterization of Irradiated Highly Embrittled Weld
Open the PDF for Use of Mini-CT Specimens for Fracture Toughness Characterization of Irradiated Highly Embrittled Weld in another window
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
Publisher: American Society of Mechanical Engineers
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
Open the PDF for Development of Generic Unirradiated Values of T 0 and RT To for Use in ASME Code Applications in another window
Topics: Accounting, ASME Standards, ASTM International, Embrittlement, Fracture toughness, Heat, Pressure, Reactor vessels, Steel, Temperature
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21141
https://doi.org/10.1115/PVP2020-21141
View Paper titled, Cracking Behavior of a Decommissioned Material in Light Water Reactor Environment
Open the PDF for Cracking Behavior of a Decommissioned Material in Light Water Reactor Environment in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21481
https://doi.org/10.1115/PVP2020-21481
View Paper titled, Fracture Toughness Tests on Western RPV Steels Using Small Scale Specimen Technique
Open the PDF for Fracture Toughness Tests on Western RPV Steels Using Small Scale Specimen Technique in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21228
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
Open the PDF for Effect of Hydrogen Content in Natural Gas Blend on the Mechanical Properties of a L485-MB Low-Alloyed Steel in another window
Topics: Alloy steel, Hydrogen, Mechanical properties, Natural gas, Steel, Pressure, Fracture (Materials), Fracture (Process), Testing, Ductility
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21446
https://doi.org/10.1115/PVP2020-21446
View Paper titled, Non-Destructive Evaluation of RPV Embrittlement by Means of the Thermoelectric Power Method
Open the PDF for Non-Destructive Evaluation of RPV Embrittlement by Means of the Thermoelectric Power Method in another window
Topics: Embrittlement, Nondestructive evaluation, Steel
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21748
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
Open the PDF for Regression Analysis of Transition Temperature Shift Database for the Core Region Beltline Welds of WWER-1000 RPVs in another window
Topics: Brittleness, Databases, Embrittlement, Phase transition temperature, Radiation (Physics), Regression analysis, Surveillance, Temperature, Welded joints, Silicon
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21185
https://doi.org/10.1115/PVP2020-21185
View Paper titled, A Code Case Concerning the Effect of Embrittlement on Index Temperature Metrics
Open the PDF for A Code Case Concerning the Effect of Embrittlement on Index Temperature Metrics in another window
Topics: Embrittlement, Temperature, Accounting, Fracture toughness, Nuclear power stations, Safety, Uncertainty