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Journal Articles

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

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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 Articletitled, 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

Verification of Probabilistic Fracture Mechanics Analysis Code for Reactor Pressure Vessel

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Yinsheng Li, Genshichiro Katsumata, Koichi Masaki, Shotaro Hayashi, Yu Itabashi, Masaki Nagai, Masahide Suzuki, Yasuhiro Kanto
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. August 2021, 143(4): 041501.
Paper No: PVT-18-1049
https://doi.org/10.1115/1.4049693
Published Online: February 11, 2021
View Articletitled, Verification of Probabilistic Fracture Mechanics Analysis Code for Reactor Pressure Vessel
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Topics: Embrittlement, Fracture (Materials), Fracture mechanics, Irradiation (Radiation exposure), Neutrons, Probability, Reactor vessels, Transients (Dynamics), Fracture (Process), Structural elements (Construction)
Journal Articles

Application of Probabilistic Fracture Mechanics to Reactor Pressure Vessel Using PASCAL4 Code

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Kai Lu, Jinya Katsuyama, Yinsheng Li, Shinobu Yoshimura
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2021, 143(2): 021505.
Paper No: PVT-20-1061
https://doi.org/10.1115/1.4048103
Published Online: October 5, 2020
View Articletitled, Application of Probabilistic Fracture Mechanics to Reactor Pressure Vessel Using PASCAL4 Code
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Topics: Embrittlement, Failure, Fracture (Materials), Fracture mechanics, Irradiation (Radiation exposure), Neutron flux, Neutrons, Nondestructive evaluation, Reactor vessels, Transients (Dynamics)
Journal Articles

Guideline on Probabilistic Fracture Mechanics Analysis for Japanese Reactor Pressure Vessels

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Jinya Katsuyama, Kazuya Osakabe, Shumpei Uno, Yinsheng Li, Shinobu Yoshimura
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2020, 142(2): 021205.
Paper No: PVT-19-1082
https://doi.org/10.1115/1.4045874
Published Online: February 24, 2020
View Articletitled, Guideline on Probabilistic Fracture Mechanics Analysis for Japanese Reactor Pressure Vessels
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Topics: Failure, Fracture (Materials), Fracture toughness, Neutrons, Reactor vessels, Transients (Dynamics), Fracture mechanics, Fracture (Process), Embrittlement, Irradiation (Radiation exposure)
Journal Articles

Methodology for Estimating Thermal and Neutron Embrittlement of Austenitic Stainless Steel Welds During Service in Light Water Reactors

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O. K. Chopra, A. S. Rao
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Review Articles
J. Pressure Vessel Technol. August 2016, 138(4): 040802.
Paper No: PVT-15-1166
https://doi.org/10.1115/1.4031910
Published Online: April 28, 2016
View Articletitled, Methodology for Estimating Thermal and Neutron Embrittlement of Austenitic Stainless Steel Welds During Service in Light Water Reactors
Open the PDF for Methodology for Estimating Thermal and Neutron Embrittlement of Austenitic Stainless Steel Welds During Service in Light Water Reactors in another window
Topics: Embrittlement, Ferrites (Magnetic materials), Fracture toughness, Welded joints, Neutrons, Temperature
Journal Articles

Methodology for Estimating Thermal and Neutron Embrittlement of Cast Austenitic Stainless Steels During Service in Light Water Reactors

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O. K. Chopra, A. S. Rao
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Review Articles
J. Pressure Vessel Technol. August 2016, 138(4): 040801.
Paper No: PVT-15-1130
https://doi.org/10.1115/1.4031909
Published Online: April 28, 2016
View Articletitled, Methodology for Estimating Thermal and Neutron Embrittlement of Cast Austenitic Stainless Steels During Service in Light Water Reactors
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Topics: Embrittlement, Ferrites (Magnetic materials), Fracture toughness, Neutrons, Temperature, Light water reactors
Journal Articles

Deterministic and Probabilistic Fracture Mechanics Analysis for Structural Integrity Assessment of Pressurized Water Reactor Pressure Vessel

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Kuan-Rong Huang, Chin-Cheng Huang, Hsiung-Wei Chou
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. June 2016, 138(3): 031202.
Paper No: PVT-15-1089
https://doi.org/10.1115/1.4032110
Published Online: February 8, 2016
View Articletitled, Deterministic and Probabilistic Fracture Mechanics Analysis for Structural Integrity Assessment of Pressurized Water Reactor Pressure Vessel
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Topics: Embrittlement, Fracture (Materials), Fracture mechanics, Pressure, Pressure vessels, Pressurized water reactors, Probability, Radiation (Physics), Reliability, Stress
Journal Articles

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

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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 Articletitled, 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

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

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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 Articletitled, 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

Mechanical and Microstructural Characterization of Heat-Affected Zone Materials of Reactor Pressure Vessel

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Jinya Katsuyama, Tohru Tobita, Yutaka Nishiyama, Kunio Onizawa
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Materials And Fabrication
J. Pressure Vessel Technol. June 2012, 134(3): 031402.
https://doi.org/10.1115/1.4005868
Published Online: May 18, 2012
View Articletitled, Mechanical and Microstructural Characterization of Heat-Affected Zone Materials of Reactor Pressure Vessel
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Topics: Base metals, Fracture toughness, Grain size, Heat, Heat treating (Metalworking), Mechanical properties, Reactor vessels, Steel, Surveillance, Temperature
Journal Articles

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

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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 Articletitled, 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
Journal Articles

Prediction of Fracture Appearance Transition Temperature of 2.25Cr-1Mo Steel Used in Hot-Wall Hydrofining Reactors

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Jinzhu Tan, Wenlong Huang, Y. J. Chao
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. November 2006, 128(4): 566–571.
https://doi.org/10.1115/1.2349569
Published Online: October 24, 2005
View Articletitled, Prediction of Fracture Appearance Transition Temperature of 2.25Cr-1Mo Steel Used in Hot-Wall Hydrofining Reactors
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Topics: Embrittlement, Fracture (Materials), Fracture (Process), Grain boundaries, Steel, Augers, Electron spectroscopy, Phase transition temperature, Impact testing
Journal Articles

Information Fusion Technique for Evaluating Radiation Embrittlement of Reactor Pressure Vessel Steels

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J. A. Wang, S. Konduri, N. S. V. Rao
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Article
J. Pressure Vessel Technol. February 2005, 127(1): 98–104.
https://doi.org/10.1115/1.1858926
Published Online: March 15, 2005
View Articletitled, Information Fusion Technique for Evaluating Radiation Embrittlement of Reactor Pressure Vessel Steels
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Topics: Boiling water reactors, Embrittlement, Uncertainty, Radiation (Physics), Steel
Journal Articles

Probability of Fracture and Life Extension Estimate of the High-Flux Isotope Reactor Vessel

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S.-J. Chang
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. August 1998, 120(3): 290–296.
https://doi.org/10.1115/1.2842060
Published Online: August 1, 1998
View Articletitled, Probability of Fracture and Life Extension Estimate of the High-Flux Isotope Reactor Vessel
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Topics: Fracture (Materials), Isotopes, Life extension, Probability, Reactor vessels, Vessels, Fracture (Process), Computation, Failure, Hydrostatic pressure
Journal Articles

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

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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 Articletitled, 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

A Creep Damage Estimation Method for In-Service Fossil Fuel Boiler Superheater Tubes

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F. Nogata, H. Takahashi
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 1995, 117(1): 14–18.
https://doi.org/10.1115/1.2842083
Published Online: February 1, 1995
View Articletitled, A Creep Damage Estimation Method for In-Service Fossil Fuel Boiler Superheater Tubes
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Topics: Boiler tubes, Creep, Damage, Fossil fuels, Etching, Fracture toughness, Grain boundaries, Boilers, Embrittlement, High temperature
Journal Articles

Prediction of Fracture Toughness K IC Transition Curves of Pressure Vessel Steels From Charpy V-Notch Impact Test Results

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T. Iwadate, Y. Tanaka, H. Takemata
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. November 1994, 116(4): 353–358.
https://doi.org/10.1115/1.2929601
Published Online: November 1, 1994
View Articletitled, Prediction of Fracture Toughness K IC Transition Curves of Pressure Vessel Steels From Charpy V-Notch Impact Test Results
Open the PDF for Prediction of Fracture Toughness K IC Transition Curves of Pressure Vessel Steels From Charpy V-Notch Impact Test Results in another window
Topics: Fracture toughness, Impact testing, Pressure vessels, Steel, Temperature, Reactor vessels, Alloys, ASTM International, Embrittlement, Engineers
Journal Articles

Verification of Warm Prestressing Effect Under a Pressurized Thermal Shock (PTS) Event

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H. Okamura, G. Yagawa, T. Hidaka, Y. Urabe, M. Satoh, M. Tomimatsu, M. Iida
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. August 1994, 116(3): 267–273.
https://doi.org/10.1115/1.2929586
Published Online: August 1, 1994
View Articletitled, Verification of Warm Prestressing Effect Under a Pressurized Thermal Shock (PTS) Event
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Topics: Cooling, Electromagnetic scattering, Embrittlement, Fracture (Materials), Fracture (Process), Fracture toughness, Irradiation (Radiation exposure), Neutrons, Pressurized water reactors, Reactor vessels
Journal Articles

Probability of Fracture for HFIR Pressure Vessel Caused by Random Crack Size or by Random Toughness

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S.-J. Chang
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 1994, 116(1): 24–29.
https://doi.org/10.1115/1.2929554
Published Online: February 1, 1994
View Articletitled, Probability of Fracture for HFIR Pressure Vessel Caused by Random Crack Size or by Random Toughness
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Topics: Fracture (Materials), Fracture toughness, Pressure vessels, Probability, Pressure, Vessels, Accidents, Embrittlement, Fluid structure interaction, Fracture mechanics
Journal Articles

Prediction of the Remaining Life of High-Temperature/Pressure Reactors Made of Cr-Mo Steels

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T. Iwadate, J. Watanabe, Y. Tanaka
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. August 1985, 107(3): 230–238.
https://doi.org/10.1115/1.3264441
Published Online: August 1, 1985
View Articletitled, Prediction of the Remaining Life of High-Temperature/Pressure Reactors Made of Cr-Mo Steels
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Topics: High temperature, Pressure, Steel, Embrittlement, Fracture (Materials), Pressure vessels, Brittle fracture, Creep, Databases, Fracture toughness