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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

Verification of Probabilistic Fracture Mechanics Analysis Code for Reactor Pressure Vessel

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 Article titled, 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

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 Article titled, 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

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 Article titled, 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

An Investigation of the Structural Integrity of a Reactor Pressure Vessel Using Three-Dimensional Computational Fluid Dynamics and Finite Element Method Based Probabilistic Pressurized Thermal Shock Analysis for Optimizing Maintenance Strategy

Xiaoyong Ruan, Toshiki Nakasuji, Kazunori Morishita
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. October 2018, 140(5): 051302.
Paper No: PVT-17-1134
https://doi.org/10.1115/1.4040698
Published Online: August 22, 2018
View Article titled, An Investigation of the Structural Integrity of a Reactor Pressure Vessel Using Three-Dimensional Computational Fluid Dynamics and Finite Element Method Based Probabilistic Pressurized Thermal Shock Analysis for Optimizing Maintenance Strategy
Open the PDF for An Investigation of the Structural Integrity of a Reactor Pressure Vessel Using Three-Dimensional Computational Fluid Dynamics and Finite Element Method Based Probabilistic Pressurized Thermal Shock Analysis for Optimizing Maintenance Strategy in another window
Topics: Computational fluid dynamics, Cooling, Finite element methods, Fracture (Materials), Maintenance, Plumes (Fluid dynamics), Probability, Simulation, Stress, Stress analysis (Engineering)
Journal Articles

Applicability of Miniature Compact Tension Specimens for Fracture Toughness Evaluation of Highly Neutron Irradiated Reactor Pressure Vessel Steels

Yoosung Ha, Tohru Tobita, Takuyo Ohtsu, Hisashi Takamizawa, Yutaka Nishiyama
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. October 2018, 140(5): 051402.
Paper No: PVT-18-1039
https://doi.org/10.1115/1.4040642
Published Online: August 2, 2018
View Article titled, Applicability of Miniature Compact Tension Specimens for Fracture Toughness Evaluation of Highly Neutron Irradiated Reactor Pressure Vessel Steels
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Topics: Fracture toughness, Neutrons, Steel, Temperature, Reactor vessels, Tension, Electromagnetic scattering
Journal Articles

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

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 Article titled, 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

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 Article titled, 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

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 Article titled, 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

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

Residual Stress Characterization in a Dissimilar Metal Weld Nuclear Reactor Piping System Mock Up

Matthew Kerr, Michael B. Prime, Hunter Swenson, Miles A. Buechler, Michael Steinzig, Bjorn Clausen, Thomas Sisneros
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. August 2013, 135(4): 041205.
Paper No: PVT-12-1086
https://doi.org/10.1115/1.4024446
Published Online: June 11, 2013
View Article titled, Residual Stress Characterization in a Dissimilar Metal Weld Nuclear Reactor Piping System Mock Up
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Topics: Stress, Metals, Neutrons, Neutron diffraction, Drilling
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

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
Journal Articles

Comparison of Neutron and Synchrotron Diffraction Measurements of Residual Stress in Bead-on-Plate Weldments

Anna M. Paradowska, John W. H. Price, Trevor R. Finlayson, Ulrich Lienert, Raafat Ibrahim
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 2010, 132(1): 011502.
https://doi.org/10.1115/1.4000344
Published Online: January 4, 2010
View Article titled, Comparison of Neutron and Synchrotron Diffraction Measurements of Residual Stress in Bead-on-Plate Weldments
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Topics: Diffraction, Stress, Welding, Neutrons
Journal Articles

Surface and Bulk Residual Stress in Ti6Al4V Welded Aerospace Tanks

G. Bruno, B. D. Dunn
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Technical Papers
J. Pressure Vessel Technol. August 2004, 126(3): 284–292.
https://doi.org/10.1115/1.1763932
Published Online: August 18, 2004
View Article titled, Surface and Bulk Residual Stress in Ti6Al4V Welded Aerospace Tanks
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Topics: Neutron diffraction, Stress, X-rays, Neutrons, X-ray diffraction, Aerospace industry
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

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

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 Article titled, 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

Residual Stresses in Steel and Zirconium Weldments

J. H. Root, C. E. Coleman, J. W. Bowden, M. Hayashi
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. May 1997, 119(2): 137–141.
https://doi.org/10.1115/1.2842274
Published Online: May 1, 1997
View Article titled, Residual Stresses in Steel and Zirconium Weldments
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Topics: Residual stresses, Steel, Zirconium, Neutron diffraction, Stress, Electron beam welding, Welding, Cathode ray oscilloscopes, Cracking (Materials), Electron beams
Journal Articles

Prevention of Nonductile Fracture in 6061-T6 Aluminum Nuclear Pressure Vessels

G. T. Yahr
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. May 1997, 119(2): 150–156.
https://doi.org/10.1115/1.2842276
Published Online: May 1, 1997
View Article titled, Prevention of Nonductile Fracture in 6061-T6 Aluminum Nuclear Pressure Vessels
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Topics: Aluminum, Fracture (Materials), Reactor vessels, Construction, Fracture (Process), Boilers, Fracture toughness, Irradiation (Radiation exposure), Low temperature, Mechanical engineers
Journal Articles

Ramberg-Osgood Strain-Hardening Characterization of an ASTM A302-B Steel

L. A. James
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. November 1995, 117(4): 341–345.
https://doi.org/10.1115/1.2842133
Published Online: November 1, 1995
View Article titled, Ramberg-Osgood Strain-Hardening Characterization of an ASTM A302-B Steel
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Topics: ASTM International, Steel, Work hardening, Temperature, Irradiation (Radiation exposure), Neutrons