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Journal Articles

Bayesian Analysis of Japanese Pressurized Water Reactor Surveillance Data for Irradiation Embrittlement Prediction

Hisashi Takamizawa, Yutaka Nishiyama
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. October 2021, 143(5): 051502.
Paper No: PVT-20-1142
https://doi.org/10.1115/1.4050317
Published Online: March 22, 2021
View Article titled, Bayesian Analysis of Japanese Pressurized Water Reactor Surveillance Data for Irradiation Embrittlement Prediction
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Topics: Embrittlement, Fluence (Radiation measurement), Irradiation (Radiation exposure), Neutrons, Pressurized water reactors, Surveillance, Steel, Temperature, Uncertainty
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
Journal Articles

Probabilistic Structural Integrity Analysis of Reactor Pressure Vessels During Pressurized Thermal Shock Events

Koichi Masaki, Jinya Katsuyama, Kunio Onizawa
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. February 2014, 136(1): 011208.
Paper No: PVT-13-1034
https://doi.org/10.1115/1.4025615
Published Online: November 27, 2013
View Article titled, Probabilistic Structural Integrity Analysis of Reactor Pressure Vessels During Pressurized Thermal Shock Events
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Topics: Fracture (Materials), Probability, Reactor vessels, Thermal shock, Transients (Dynamics), Temperature, Sensitivity analysis, Fracture mechanics, Neutrons, Fluence (Radiation measurement)
Journal Articles

Boiling Water Reactor Pressure Vessel Integrity Evaluation by Probabilistic Fracture Mechanics (PVP2010-25195)

Bo-Yi Chen, Chin-Cheng Huang, Hsoung-Wei Chou, Ru-Feng Liu, Hsien-Chou Lin
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. February 2013, 135(1): 011206.
Paper No: PVT-12-1003
https://doi.org/10.1115/1.4007292
Published Online: December 17, 2012
View Article titled, Boiling Water Reactor Pressure Vessel Integrity Evaluation by Probabilistic Fracture Mechanics (PVP2010-25195)
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Topics: Boiling water reactors, Design, Failure, Fluence (Radiation measurement), Fracture mechanics, Neutrons, Nuclear power stations, Pressure vessels, Probability, Transients (Dynamics)
Journal Articles

Estimation of Master Curve Based RT TO Reference Temperature From CVN Data

Kim R. W. Wallin, Gerhard Nagel, Elisabeth Keim, Dieter Siegele
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. August 2007, 129(3): 420–425.
https://doi.org/10.1115/1.2748823
Published Online: June 8, 2006
View Article titled, Estimation of Master Curve Based RT TO Reference Temperature From CVN Data
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Topics: Fluence (Radiation measurement), Fracture toughness, Temperature, Welded joints, Pressure vessels, Steel, ASME Standards
Journal Articles

Evaluation Procedures for Irradiation Effects and Sodium Environmental Effects for the Structural Design of Japanese Fast Breeder Reactors

Tai Asayama, Yasuhiro Abe, Noriko Miyaji, Mamoru Koi, Tomohiro Furukawa, Eiichi Yoshida
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Technical Papers
J. Pressure Vessel Technol. February 2001, 123(1): 49–57.
https://doi.org/10.1115/1.1338119
Published Online: October 27, 2000
View Article titled, Evaluation Procedures for Irradiation Effects and Sodium Environmental Effects for the Structural Design of Japanese Fast Breeder Reactors
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Topics: Corrosion, Creep, Design, Irradiation (Radiation exposure), Mechanical properties, Neutrons, Sodium, Steel, Fluence (Radiation measurement), Breeder reactors
Journal Articles

Alternative Method of RT NDT Determination for Some Reactor Vessel Weld Metals Validated by Fracture Toughness Data

K. K. Yoon
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. November 1995, 117(4): 378–382.
https://doi.org/10.1115/1.2842139
Published Online: November 1, 1995
View Article titled, Alternative Method of RT NDT Determination for Some Reactor Vessel Weld Metals Validated by Fracture Toughness Data
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Topics: Fracture toughness, Metals, Reactor vessels, Temperature, Ductility, Weight (Mass), ASME Standards, ASTM International, Embrittlement, Fluence (Radiation measurement)
Journal Articles

Application of the Failure Assessment Diagram to the Evaluation of Pressure-Temperature Limits for a Pressurized Water Reactor

K. K. Yoon, J. M. Bloom, W. A. Pavinich, H. W. Slager
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. May 1985, 107(2): 192–196.
https://doi.org/10.1115/1.3264433
Published Online: May 1, 1985
View Article titled, Application of the Failure Assessment Diagram to the Evaluation of Pressure-Temperature Limits for a Pressurized Water Reactor
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Topics: Failure, Pressure, Pressurized water reactors, Temperature, Fracture mechanics, Vessels, Coolants, Fluence (Radiation measurement), Fracture toughness, Materials properties
Journal Articles

Lifetime Analysis of Fusion Reactor First Wall Components

R. D. Watson, R. R. Peterson, W. G. Wolfer
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. May 1983, 105(2): 144–152.
https://doi.org/10.1115/1.3264256
Published Online: May 1, 1983
View Article titled, Lifetime Analysis of Fusion Reactor First Wall Components
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Topics: Creep, Embrittlement, Fluence (Radiation measurement), Flux (Metallurgy), Fracture (Materials), Fracture mechanics, Fusion reactors, Heat, Irradiation (Radiation exposure), Neutrons
Journal Articles

Further Observations on A533-B Steel Plate Tailored for Improved Radiation Embrittlement Resistance

J. R. Hawthorne
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. May 1976, 98(2): 111–117.
https://doi.org/10.1115/1.3454347
Published Online: May 1, 1976
View Article titled, Further Observations on A533-B Steel Plate Tailored for Improved Radiation Embrittlement Resistance
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Topics: Embrittlement, Radiation (Physics), Steel, Copper, Temperature, Ductility, Irradiation (Radiation exposure), Fluence (Radiation measurement), Heat treating (Metalworking), Plates (structures)