Search Results | ASME Digital Collection

1-20 of 23

Sort by

Sort Order Select

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

Topics: Embrittlement, Fracture toughness, Radiation (Physics)

Proceedings Papers

Specimen Size and Geometry Effects on the Master Curve Fracture Toughness Measurements of EUROFER97 and F82H Steels

Xiang (Frank) Chen, Mikhail A. Sokolov, Sehila M. Gonzalez De Vicente, Yutai Katoh

Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A048, July 17–22, 2022

Paper No: PVP2022-84514

DOI: https://doi.org/10.1115/PVP2022-84514

View Paper

Topics: Fracture toughness, Geometry, Size effect, Steel

Proceedings Papers

Post-Irradiation Evaluation of Eurofer97 Fracture Toughness Using Miniature Multinotch Bend Bar Specimens

Xiang Chen, Logan A. Clowers, Tim Graening, Arunodaya Bhattacharya, Anne A. Campbell, Janet Robertson, Josina W. Geringer, Mikhail A. Sokolov, Yutai Katoh, Michael Rieth

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A059, August 3, 2020

Paper No: PVP2020-21312

DOI: https://doi.org/10.1115/PVP2020-21312

View Paper

Topics: Fracture toughness, Irradiation (Radiation exposure)

Proceedings Papers

Master Curve Fracture Toughness Characterization of Eurofer97 Steel Variants Using Miniature Multi-Notch Bend Bar Specimens for Fusion Applications

Xiang Chen, Mikhail A. Sokolov, Arunodaya Bhattacharya, Logan N. Clowers, Tim Graening, Yutai Katoh, Michael Rieth

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A036, July 14–19, 2019

Paper No: PVP2019-93797

DOI: https://doi.org/10.1115/PVP2019-93797

View Paper

Topics: Fracture toughness, Steel, Testing, Weibull distribution

Proceedings Papers

Use of Mini-CT Specimens for Fracture Toughness Characterization of Low Upper-Shelf Linde 80 Weld Before and After Irradiation

Mikhail A. Sokolov

Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A070, July 15–20, 2018

Paper No: PVP2018-84804

DOI: https://doi.org/10.1115/PVP2018-84804

View Paper

Topics: Fracture toughness, Irradiation (Radiation exposure), ASTM International, Geometry, Reactor vessels, Temperature

Proceedings Papers

Master Curve Fracture Toughness Characterization of Eurofer97 Using Miniature Multi-Notch Bend Bar Specimens for Fusion Applications

Xiang Chen, Mikhail A. Sokolov, Yutai Katoh, Michael Rieth, Logan N. Clowers

Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A076, July 15–20, 2018

Paper No: PVP2018-85065

DOI: https://doi.org/10.1115/PVP2018-85065

View Paper

Topics: Fracture toughness, Steel, Irradiation (Radiation exposure), Temperature, Testing, ASTM International, Damage, Dimensions, Electromagnetic scattering, Embrittlement

Proceedings Papers

Some Useful Mechanical Property Correlations for Nuclear Reactor Pressure Vessel Steels

Randy K. Nanstad, William L. Server, Mikhail A. Sokolov, G. Robert Odette, Nathan Almirall

Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A019, July 15–20, 2018

Paper No: PVP2018-84786

DOI: https://doi.org/10.1115/PVP2018-84786

View Paper

Topics: Embrittlement, Industrial research, Irradiation (Radiation exposure), Mechanical properties, Nuclear industry, Nuclear reactors, Pressure vessels, Reactor vessels, Safety, Steel

Proceedings Papers

Current Status of the Characterization of RPV Materials Harvested From the Decommissioned Zion Unit 1 Nuclear Power Plant

Thomas M. Rosseel, Mikhail A. Sokolov, Xiang Chen, Randy K. Nanstad

Proc. ASME. PVP2017, Volume 1B: Codes and Standards, V01BT01A059, July 16–20, 2017

Paper No: PVP2017-65090

DOI: https://doi.org/10.1115/PVP2017-65090

View Paper

Topics: Nuclear power stations, Base metals, Light water reactors, Mechanical properties, Atoms, Cutting, Embrittlement, Fluence (Radiation measurement), Fracture toughness, Heat

Proceedings Papers

ORNL Evaluation of Safety Cases for Two Belgian Reactor Pressure Vessels Containing Quasi-Laminar Defects

Hilda B. Klasky, B. Richard Bass, Terry L. Dickson, Sarma B. Gorti, Randy K. Nanstad, Mikhail A. Sokolov, William L. Server, Paul T. Williams

Proc. ASME. PVP2017, Volume 1A: Codes and Standards, V01AT01A045, July 16–20, 2017

Paper No: PVP2017-65305

DOI: https://doi.org/10.1115/PVP2017-65305

View Paper

Topics: Reactor vessels, Safety, Design, Fracture (Process), Transients (Dynamics), ASME Boiler and Pressure Vessel Code, ASME Standards, Coolants, Failure, Finite element analysis

Proceedings Papers

Use of Mini-CT Specimens for Fracture Toughness Characterization of Low Upper-Shelf Linde 80 Weld

Mikhail A. Sokolov

Proc. ASME. PVP2017, Volume 1A: Codes and Standards, V01AT01A069, July 16–20, 2017

Paper No: PVP2017-65904

DOI: https://doi.org/10.1115/PVP2017-65904

View Paper

Topics: Fracture toughness, Reactor vessels, Surveillance, ASME Standards, Base metals, Geometry, Temperature

Proceedings Papers

Thermal Annealing of Reactor Pressure Vessels

Mikhail A. Sokolov, William L. Server, Randy K. Nanstad

Proc. ASME. PVP2015, Volume 7: Operations, Applications and Components, V007T07A021, July 19–23, 2015

Paper No: PVP2015-45783

DOI: https://doi.org/10.1115/PVP2015-45783

View Paper

Topics: Annealing, Reactor vessels, Nuclear power stations, Service life (Equipment), Neutrons, Phase transition temperature, Radiation (Physics), Reliability, Steel, Structural elements (Construction)

Proceedings Papers

Machining Test Specimens From Harvested Zion RPV Segments

Thomas M. Rosseel, Mikhail A. Sokolov, Randy K. Nanstad

Proc. ASME. PVP2015, Volume 7: Operations, Applications and Components, V007T07A015, July 19–23, 2015

Paper No: PVP2015-45237

DOI: https://doi.org/10.1115/PVP2015-45237

View Paper

Topics: Machining, Light water reactors, Nuclear power stations, Welded joints, Cutting, Materials degradation, Nuclear decommissioning, Nuclear reactors, Power stations, Radiation damage

Proceedings Papers

Master Curve and J-R Fracture Toughness of SA508/SA533-B-1 Weld and HAZ

Randy K. Nanstad, Xiang Chen, Mikhail A. Sokolov, Barry H. Rabin, Ying Yang

Proc. ASME. PVP2013, Volume 6B: Materials and Fabrication, V06BT06A001, July 14–18, 2013

Paper No: PVP2013-97033

DOI: https://doi.org/10.1115/PVP2013-97033

View Paper

Topics: Fracture toughness, Temperature, Steel, Heat, Metals, Alloys, ASME Boiler and Pressure Vessel Code, ASTM International, Displacement, Ductile fracture

Proceedings Papers

Use of Small Specimens for Evaluation of Irradiated Materials

Mikhail A. Sokolov, Randy K. Nanstad

Proc. ASME. PVP2013, Volume 6B: Materials and Fabrication, V06BT06A057, July 14–18, 2013

Paper No: PVP2013-98089

DOI: https://doi.org/10.1115/PVP2013-98089

View Paper

Topics: Accounting, Fracture toughness, Geometry, Neutron flux, Neutrons, Phase transition temperature, Radioactive substances, Reactor vessels, Steel, Surveillance

Proceedings Papers

Ensuring the Performance of Nuclear Reactor Pressure Vessels for Long-Time Service

Randy K. Nanstad, G. Robert Odette, Mikhail A. Sokolov

Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 125-133, July 18–22, 2010

Paper No: PVP2010-25832

DOI: https://doi.org/10.1115/PVP2010-25832

View Paper

Topics: Annealing, Databases, Embrittlement, Fluence (Radiation measurement), Fracture mechanics, Irradiation (Radiation exposure), Light water reactors, Neutrons, Nickel, Nuclear power stations

Journal Articles

Heavy-Section Steel Technology and Irradiation Programs—Retrospective and Prospective Views

Randy K. Nanstad, B. Richard Bass, John G. Merkle, Claud E. Pugh, Thomas M. Rosseel, Mikhail A. Sokolov

J. Pressure Vessel Technol. December 2010, 132(6): 064001.

DOI: https://doi.org/10.1115/1.4001425

Published Online: October 14, 2010

View Article

Topics: Fracture (Materials), Fracture toughness, Irradiation (Radiation exposure), Steel, Temperature, Thermal shock, Vessels, Fracture (Process), Embrittlement, Neutrons

Proceedings Papers

Estimation of Crack-Arrest Toughness Transition and NDT Temperatures From Charpy Force-Displacement Impact Traces

Mikhail A. Sokolov

Proc. ASME. PVP2009, Volume 6: Materials and Fabrication, Parts A and B, 811-815, July 26–30, 2009

Paper No: PVP2009-77894

DOI: https://doi.org/10.1115/PVP2009-77894

View Paper

Topics: Displacement, Fracture (Materials), Fracture toughness, Temperature, Steel, Notch testing, Shapes, Temperature effects, Crack propagation, Probability

Proceedings Papers

Heavy-Section Steel Technology and Irradiation Programs: Retrospective and Prospective Views

Randy K. Nanstad, B. Richard Bass, Thomas M. Rosseel, John G. Merkle, Mikhail A. Sokolov

Proc. ASME. PVP2007, Volume 6: Materials and Fabrication, 733-752, July 22–26, 2007

Paper No: PVP2007-26677

DOI: https://doi.org/10.1115/PVP2007-26677

View Paper

Topics: Irradiation (Radiation exposure), Steel, Fracture (Materials), Fracture toughness, Fracture (Process), Thermal shock, Vessels, Neutrons, Plates (structures), Safety

Proceedings Papers

Experimental Evaluation of Deformation and Constraint Characteristics in Precracked Charpy and Other Three-Point Bend Specimens

Randy K. Nanstad, Donald E. McCabe, Mikhail A. Sokolov, John G. Merkle

Proc. ASME. PVP2007, Volume 7: Operations, Applications and Components, 259-267, July 22–26, 2007

Paper No: PVP2007-26651

DOI: https://doi.org/10.1115/PVP2007-26651

View Paper

Topics: Deformation, Temperature, Calibration, Steel, Fracture (Materials), Fracture toughness, Irradiation (Radiation exposure), Plates (structures), Reactor vessels, Surveillance

Proceedings Papers

Microstructural Banding and Biaxial Fracture Toughness Tests in a Specially Heat-Treated Reactor Pressure Vessel Steel

Randy K. Nanstad, Mikhail A. Sokolov, Philip J. Maziasz

Proc. ASME. PVP2004, Storage Tank Integrity and Materials Evaluation, 65-82, July 25–29, 2004

Paper No: PVP2004-3058

DOI: https://doi.org/10.1115/PVP2004-3058

View Paper

Topics: Fractography, Fracture toughness, Heat, Metallography, Reactor vessels, Steel

Journal citation

NARROW

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

Specimen Size and Geometry Effects on the Master Curve Fracture Toughness Measurements of EUROFER97 and F82H Steels

Post-Irradiation Evaluation of Eurofer97 Fracture Toughness Using Miniature Multinotch Bend Bar Specimens

Master Curve Fracture Toughness Characterization of Eurofer97 Steel Variants Using Miniature Multi-Notch Bend Bar Specimens for Fusion Applications

Use of Mini-CT Specimens for Fracture Toughness Characterization of Low Upper-Shelf Linde 80 Weld Before and After Irradiation

Master Curve Fracture Toughness Characterization of Eurofer97 Using Miniature Multi-Notch Bend Bar Specimens for Fusion Applications

Some Useful Mechanical Property Correlations for Nuclear Reactor Pressure Vessel Steels

Current Status of the Characterization of RPV Materials Harvested From the Decommissioned Zion Unit 1 Nuclear Power Plant

ORNL Evaluation of Safety Cases for Two Belgian Reactor Pressure Vessels Containing Quasi-Laminar Defects

Use of Mini-CT Specimens for Fracture Toughness Characterization of Low Upper-Shelf Linde 80 Weld

Thermal Annealing of Reactor Pressure Vessels

Machining Test Specimens From Harvested Zion RPV Segments

Master Curve and J-R Fracture Toughness of SA508/SA533-B-1 Weld and HAZ

Use of Small Specimens for Evaluation of Irradiated Materials

Ensuring the Performance of Nuclear Reactor Pressure Vessels for Long-Time Service

Heavy-Section Steel Technology and Irradiation Programs—Retrospective and Prospective Views

Estimation of Crack-Arrest Toughness Transition and NDT Temperatures From Charpy Force-Displacement Impact Traces

Heavy-Section Steel Technology and Irradiation Programs: Retrospective and Prospective Views

Experimental Evaluation of Deformation and Constraint Characteristics in Precracked Charpy and Other Three-Point Bend Specimens

Microstructural Banding and Biaxial Fracture Toughness Tests in a Specially Heat-Treated Reactor Pressure Vessel Steel

Journals

Conference Proceedings

eBooks

Resources

Opportunities

Journals

Conference Proceedings

eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only