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Randy K. Nanstad
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eBook Chapter

On High-Fluence Irradiation Hardening of Nine RPV Surveillance Steels in the UCSB ATR-2 Experiment: Implications for Extended-Life Embrittlement Predictions

Series: ASTM Selected Technical Papers
Publisher: ASTM International
Published: 2023
ISBN: 978-0-8031-7741-3
Open the PDF for On High-Fluence Irradiation Hardening of Nine RPV Surveillance Steels in the UCSB ATR-2 Experiment: Implications for Extended-Life Embrittlement Predictions in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84786
https://doi.org/10.1115/PVP2018-84786
View Paper titled, Some Useful Mechanical Property Correlations for Nuclear Reactor Pressure Vessel Steels
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Topics: Embrittlement, Industrial research, Irradiation (Radiation exposure), Mechanical properties, Nuclear industry, Nuclear reactors, Pressure vessels, Reactor vessels, Safety, Steel
eBook Chapter

Neutron and Thermal Embrittlement of RPV Steels: An Overview

Series: ASTM Selected Technical Papers
Publisher: ASTM International
Published: 2018
ISBN: 978-0-8031-7651-5
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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65305
https://doi.org/10.1115/PVP2017-65305
View Paper titled, ORNL Evaluation of Safety Cases for Two Belgian Reactor Pressure Vessels Containing Quasi-Laminar Defects
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Topics: Reactor vessels, Safety, Design, Fracture (Process), Transients (Dynamics), ASME Boiler and Pressure Vessel Code, ASME Standards, Coolants, Failure, Finite element analysis
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65090
https://doi.org/10.1115/PVP2017-65090
View Paper titled, Current Status of the Characterization of RPV Materials Harvested From the Decommissioned Zion Unit 1 Nuclear Power Plant
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Topics: Nuclear power stations, Base metals, Light water reactors, Mechanical properties, Atoms, Cutting, Embrittlement, Fluence (Radiation measurement), Fracture toughness, Heat
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45237
https://doi.org/10.1115/PVP2015-45237
View Paper titled, Machining Test Specimens From Harvested Zion RPV Segments
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Topics: Machining, Light water reactors, Nuclear power stations, Welded joints, Cutting, Materials degradation, Nuclear decommissioning, Nuclear reactors, Power stations, Radiation damage
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45783
https://doi.org/10.1115/PVP2015-45783
View Paper titled, Thermal Annealing of Reactor Pressure Vessels
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Topics: Annealing, Reactor vessels, Nuclear power stations, Service life (Equipment), Neutrons, Phase transition temperature, Radiation (Physics), Reliability, Steel, Structural elements (Construction)
eBook Chapter

Application of Direct Current Potential Drop for the J-Integral vs. Crack Growth Resistance Curve Characterization

Series: ASTM Selected Technical Papers
Publisher: ASTM International
Published: 2015
ISBN: 978-0-8031-7613-3
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Journal Articles

U.S. High Fluence Power Reactor Surveillance Data—Past and Future

William L. Server, Timothy C. Hardin, J. Brian Hall, Randy K. Nanstad
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2014, 136(2): 021603.
Paper No: PVT-13-1154
https://doi.org/10.1115/1.4026149
Published Online: January 30, 2014
View Article titled, U.S. High Fluence Power Reactor Surveillance Data—Past and Future
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Topics: Fluence (Radiation measurement), Light water reactors, Surveillance, Embrittlement, Pressurized water reactors
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-97033
https://doi.org/10.1115/PVP2013-97033
View Paper titled, Master Curve and J-R Fracture Toughness of SA508/SA533-B-1 Weld and HAZ
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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-98089
https://doi.org/10.1115/PVP2013-98089
View Paper titled, Use of Small Specimens for Evaluation of Irradiated Materials
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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25832
https://doi.org/10.1115/PVP2010-25832
View Paper titled, Ensuring the Performance of Nuclear Reactor Pressure Vessels for Long-Time Service
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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
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Technology Review
J. Pressure Vessel Technol. December 2010, 132(6): 064001.
https://doi.org/10.1115/1.4001425
Published Online: October 14, 2010
View Article titled, Heavy-Section Steel Technology and Irradiation Programs—Retrospective and Prospective Views
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Topics: Fracture (Materials), Fracture toughness, Irradiation (Radiation exposure), Steel, Temperature, Thermal shock, Vessels, Fracture (Process), Embrittlement, Neutrons
Proceedings Papers

IAEA Coordinated Research Project on Master Curve Approach to Monitor Fracture Toughness of RPV Steels: Final Results of the Experimental Exercise to Support Constraint Effects

Randy K. Nanstad, Milan Brumovsky, Rogelio Herna´ndez Callejas, Ferenc Gillemot, Mikhail Korshunov, Bong Sang Lee, Enrico Lucon, Marc Scibetta, Philip Minnebo, Karl-Fredrik Nilsson, Naoki Miura, Kunio Onizawa, Tapio Planman, William Server, Brian Burgos, Marta Serrano, Hans-Werner Viehrig
Proc. ASME. PVP2009, Volume 3: Design and Analysis, 573-585, July 26–30, 2009
Publisher: American Society of Mechanical Engineers
Paper No: PVP2009-78022
https://doi.org/10.1115/PVP2009-78022
View Paper titled, IAEA Coordinated Research Project on Master Curve Approach to Monitor Fracture Toughness of RPV Steels: Final Results of the Experimental Exercise to Support Constraint Effects
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Topics: Fracture toughness, Steel, Carbon reinforced plastics, Temperature, Resolution (Optics), Surveillance, ASTM International, Finite element analysis, Geometry, Modeling
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2007-26651
https://doi.org/10.1115/PVP2007-26651
View Paper titled, Experimental Evaluation of Deformation and Constraint Characteristics in Precracked Charpy and Other Three-Point Bend Specimens
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Topics: Deformation, Temperature, Calibration, Steel, Fracture (Materials), Fracture toughness, Irradiation (Radiation exposure), Plates (structures), Reactor vessels, Surveillance
Proceedings Papers

IAEA Coordinated Research Project on Master Curve Approach to Monitor Fracture Toughness of RPV Steels: Effects of Bias, Constraint, and Geometry

Randy K. Nanstad, Marc Scibetta
Proc. ASME. PVP2007, Volume 7: Operations, Applications and Components, 223-233, July 22–26, 2007
Publisher: American Society of Mechanical Engineers
Paper No: PVP2007-26231
https://doi.org/10.1115/PVP2007-26231
View Paper titled, IAEA Coordinated Research Project on Master Curve Approach to Monitor Fracture Toughness of RPV Steels: Effects of Bias, Constraint, and Geometry
Open the PDF for IAEA Coordinated Research Project on Master Curve Approach to Monitor Fracture Toughness of RPV Steels: Effects of Bias, Constraint, and Geometry in another window
Topics: Fracture toughness, Geometry, Steel, Temperature, Carbon reinforced plastics, Fracture (Materials), Testing, Finite element analysis, Light water reactors, Modeling
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2007-26677
https://doi.org/10.1115/PVP2007-26677
View Paper titled, Heavy-Section Steel Technology and Irradiation Programs: Retrospective and Prospective Views
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Topics: Irradiation (Radiation exposure), Steel, Fracture (Materials), Fracture toughness, Fracture (Process), Thermal shock, Vessels, Neutrons, Plates (structures), Safety
Journal Articles

International Atomic Energy Agency Coordinated Research Projects on Structural Integrity of Reactor Pressure Vessels

William L. Server, Randy K. Nanstad
Journal: Journal of ASTM International
Publisher: ASTM International
Article Type: Research-Article
J. ASTM Int.. July 2009, 6(7): 1–17.
https://doi.org/10.1520/JAI102096
Published Online: July 1, 2009
View Article titled, International Atomic Energy Agency Coordinated Research Projects on Structural Integrity of Reactor Pressure Vessels
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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2004-3058
https://doi.org/10.1115/PVP2004-3058
View Paper titled, Microstructural Banding and Biaxial Fracture Toughness Tests in a Specially Heat-Treated Reactor Pressure Vessel Steel
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Topics: Fractography, Fracture toughness, Heat, Metallography, Reactor vessels, Steel
Proceedings Papers

On Bias in T o Values Derived With Compact and PCVN Specimens

Mikhail A. Sokolov, Randy K. Nanstad
Proc. ASME. PVP2004, Fracture Methodologies and Manufacturing Processes, 115-120, July 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: PVP2004-2306
https://doi.org/10.1115/PVP2004-2306
View Paper titled, On Bias in T o Values Derived With Compact and PCVN Specimens
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Topics: Fracture toughness, Geometry, Irradiation (Radiation exposure), Phase transition temperature, Pressure vessels, Reactor vessels, Steel, Surveillance, Testing