1-11 of 11
William L. Server
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

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
PDF
Topics: Embrittlement, Industrial research, Irradiation (Radiation exposure), Mechanical properties, Nuclear industry, Nuclear reactors, Pressure vessels, Reactor vessels, Safety, Steel
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
PDF
Topics: Reactor vessels, Safety, Design, Fracture (Process), Transients (Dynamics), ASME Boiler and Pressure Vessel Code, ASME Standards, Coolants, Failure, Finite element analysis
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
PDF
Topics: Annealing, Reactor vessels, Nuclear power stations, Service life (Equipment), Neutrons, Phase transition temperature, Radiation (Physics), Reliability, Steel, Structural elements (Construction)
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
Article Type: Research-Article
J. Pressure Vessel Technol. April 2014, 136(2): 021603.
Paper No: PVT-13-1154
DOI: https://doi.org/10.1115/1.4026149
Published Online: January 30, 2014
View Article
PDF
Topics: Fluence (Radiation measurement), Light water reactors, Surveillance, Embrittlement, Pressurized water reactors
eBook Chapter

PWR Reactor Vessel Integrity and Internals Aging Management

Publisher: ASME Press
Published: 2014
ISBN: 9780791860199
View chapter
PDF
Topics: Pressurized water reactors, Reactor vessels
Proceedings Papers

Microstructural Changes Related to Through-Wall Attenuation of Neutron Irradiation Embrittlement

Naoki Soneda, Kenji Nishida, Kenji Dohi, Akiyoshi Nomoto, William L. Server, Milan Brumovsky, Milos Kytka, Jack Spanner
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 119-124, July 18–22, 2010
Paper No: PVP2010-25636
DOI: https://doi.org/10.1115/PVP2010-25636
View Paper
PDF
Topics: Embrittlement, Irradiation (Radiation exposure), Neutrons, Copper, Mechanical properties, Atoms, Fluence (Radiation measurement), Steel, Fracture toughness, Metals
Proceedings Papers

IAEA Coordinated Research Project on Master Curve Approach to Monitor Fracture Toughness of RPV Steels: Effect of Loading Rate

Hans-Werner Viehrig, Enrico Lucon, William L. Server
Proc. ASME. PVP2009, Volume 3: Design and Analysis, 467-472, July 26–30, 2009
Paper No: PVP2009-77668
DOI: https://doi.org/10.1115/PVP2009-77668
View Paper
PDF
Topics: Fracture toughness, Steel, ASTM International, Brittleness, Dynamic testing (Engineering), Dynamic testing (Materials), Pendulums
Proceedings Papers

Application of Master Curve Data for Reactor Vessel Steels

William L. Server, Timothy J. Griesbach, Stan T. Rosinski
Proc. ASME. PVP2003, Application of Fracture Mechanics in Failure Assessment, 99-102, July 20–24, 2003
Paper No: PVP2003-2013
DOI: https://doi.org/10.1115/PVP2003-2013
View Paper
PDF
Topics: Reactor vessels, Steel, Fracture toughness, Databases, ASME Standards, Brittleness, Forging, Geometry, Phase transition temperature, Pressure vessels
Proceedings Papers

Neutron Embrittlement Aging Management of Nuclear Reactor Pressure Vessels

William L. Server
Proc. ASME. PVP2003, Aging Management and Component Analysis, 17-28, July 20–24, 2003
Paper No: PVP2003-2150
DOI: https://doi.org/10.1115/PVP2003-2150
View Paper
PDF
Topics: Embrittlement, Neutrons, Nuclear reactors, Pressure vessels, Fracture toughness, ASTM International, Reactor vessels, Phase transition temperature, Surveillance, Vessels
Proceedings Papers

Assessment of U.S. Embrittlement Trend Equations Considering the Latest Available Surveillance Data

William L. Server, Randy G. Lott, Stan T. Rosinski
Proc. ASME. PVP2004, Storage Tank Integrity and Materials Evaluation, 19-24, July 25–29, 2004
Paper No: PVP2004-3053
DOI: https://doi.org/10.1115/PVP2004-3053
View Paper
PDF
Topics: Embrittlement, Surveillance, Boiling water reactors, ASTM International, Databases, Heat, Pressurized water reactors, Thermal shock
Proceedings Papers

A Probabilistic Approach to Heatup and Cooldown Operating Limits for a Nuclear Pressure Vessel

Randy G. Lott, William L. Server
Proc. ASME. PVP2004, Storage Tank Integrity and Materials Evaluation, 123-128, July 25–29, 2004
Paper No: PVP2004-3062
DOI: https://doi.org/10.1115/PVP2004-3062
View Paper
PDF
Topics: Reactor vessels, Vessels, Pressure, Failure, Stress, Risk, Temperature, Fracture mechanics, Fracture (Materials), Fracture toughness