1-20 of 26
Irradiation (Radiation exposure)
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
Journal Articles

Large-Scale Modeling of Damage and Failure of Nuclear Graphite Moderated Reactor

Ahmadreza Farrokhnia, Andrey P. Jivkov, Graham Hall, Paul Mummery
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. June 2022, 144(3): 031502.
Paper No: PVT-20-1195
https://doi.org/10.1115/1.4053478
Published Online: February 10, 2022
View Article titled, Large-Scale Modeling of Damage and Failure of Nuclear Graphite Moderated Reactor
Open the PDF for Large-Scale Modeling of Damage and Failure of Nuclear Graphite Moderated Reactor in another window
Topics: Bricks, Damage, Failure, Graphite, Stress, Fuels, Modeling, Irradiation (Radiation exposure), Fracture (Process)
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
Open the PDF for Bayesian Analysis of Japanese Pressurized Water Reactor Surveillance Data for Irradiation Embrittlement Prediction in another window
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
Open the PDF for Verification of Probabilistic Fracture Mechanics Analysis Code for Reactor Pressure Vessel in another window
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
Open the PDF for Application of Probabilistic Fracture Mechanics to Reactor Pressure Vessel Using PASCAL4 Code in another window
Topics: Embrittlement, Failure, Fracture (Materials), Fracture mechanics, Irradiation (Radiation exposure), Neutron flux, Neutrons, Nondestructive evaluation, Reactor vessels, Transients (Dynamics)
Journal Articles

Technical Basis Part 2 for Code Case N-889: Reference Stress Corrosion Crack Growth Rate Curves for Irradiated Austenitic Stainless Steels in Light Water Reactor Environments

Ernest D. Eason, Raj Pathania, Anders Jenssen, Dennis P. Weakland
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2021, 143(2): 021202.
Paper No: PVT-19-1261
https://doi.org/10.1115/1.4047878
Published Online: September 15, 2020
View Article titled, Technical Basis Part 2 for Code Case N-889: Reference Stress Corrosion Crack Growth Rate Curves for Irradiated Austenitic Stainless Steels in Light Water Reactor Environments
Open the PDF for Technical Basis Part 2 for Code Case N-889: Reference Stress Corrosion Crack Growth Rate Curves for Irradiated Austenitic Stainless Steels in Light Water Reactor Environments in another window
Topics: Calibration, Fracture (Materials), Heat, Inspection, Irradiation (Radiation exposure), Light water reactors, Pressurized water reactors, Stainless steel, Stress corrosion cracking, Yield stress
Journal Articles

Technical Basis Part 1 for Code Case N-889: Data Selection and Modeling of Stress Corrosion Crack Growth Rates for Irradiated Austenitic Stainless Steels in Light Water Reactor Environments

Ernest D. Eason, Raj Pathania, Anders Jenssen
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2021, 143(2): 021201.
Paper No: PVT-19-1260
https://doi.org/10.1115/1.4047879
Published Online: September 15, 2020
View Article titled, Technical Basis Part 1 for Code Case N-889: Data Selection and Modeling of Stress Corrosion Crack Growth Rates for Irradiated Austenitic Stainless Steels in Light Water Reactor Environments
Open the PDF for Technical Basis Part 1 for Code Case N-889: Data Selection and Modeling of Stress Corrosion Crack Growth Rates for Irradiated Austenitic Stainless Steels in Light Water Reactor Environments in another window
Topics: Calibration, Heat, Modeling, Stainless steel, Stress corrosion cracking, Fracture (Materials), Yield stress, Irradiation (Radiation exposure), Light water reactors, Fittings
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
Open the PDF for Guideline on Probabilistic Fracture Mechanics Analysis for Japanese Reactor Pressure Vessels in another window
Topics: Failure, Fracture (Materials), Fracture toughness, Neutrons, Reactor vessels, Transients (Dynamics), Fracture mechanics, Fracture (Process), Embrittlement, Irradiation (Radiation exposure)
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
Open the PDF for Deterministic and Probabilistic Fracture Mechanics Analysis for Structural Integrity Assessment of Pressurized Water Reactor Pressure Vessel in another window
Topics: Embrittlement, Fracture (Materials), Fracture mechanics, Pressure, Pressure vessels, Pressurized water reactors, Probability, Radiation (Physics), Reliability, Stress
Journal Articles

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

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 Article titled, Mechanical and Microstructural Characterization of Heat-Affected Zone Materials of Reactor Pressure Vessel
Open the PDF for Mechanical and Microstructural Characterization of Heat-Affected Zone Materials of Reactor Pressure Vessel in another window
Topics: Base metals, Fracture toughness, Grain size, Heat, Heat treating (Metalworking), Mechanical properties, Reactor vessels, Steel, Surveillance, Temperature
Journal Articles

A Risk-Informed Methodology for ASME Section XI, Appendix G

Ronald Gamble, William Server, Bruce Bishop, Nathan Palm, Carol Heinecke
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. June 2012, 134(3): 031002.
https://doi.org/10.1115/1.4006580
Published Online: May 18, 2012
View Article titled, A Risk-Informed Methodology for ASME Section XI, Appendix G
Open the PDF for A Risk-Informed Methodology for ASME Section XI, Appendix G in another window
Topics: Boiling water reactors, Heat, Leakage, Pressure, Pressurized water reactors, Risk, Temperature, Vessels, Irradiation (Radiation exposure), Reactor vessels
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
Open the PDF for Heavy-Section Steel Technology and Irradiation Programs—Retrospective and Prospective Views in another window
Topics: Fracture (Materials), Fracture toughness, Irradiation (Radiation exposure), Steel, Temperature, Thermal shock, Vessels, Fracture (Process), Embrittlement, Neutrons
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
Open the PDF for Evaluation Procedures for Irradiation Effects and Sodium Environmental Effects for the Structural Design of Japanese Fast Breeder Reactors in another window
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
Open the PDF for Probability of Fracture and Life Extension Estimate of the High-Flux Isotope Reactor Vessel in another window
Topics: Fracture (Materials), Isotopes, Life extension, Probability, Reactor vessels, Vessels, Fracture (Process), Computation, Failure, Hydrostatic pressure
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
Open the PDF for Prevention of Nonductile Fracture in 6061-T6 Aluminum Nuclear Pressure Vessels in another window
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
Open the PDF for Ramberg-Osgood Strain-Hardening Characterization of an ASTM A302-B Steel in another window
Topics: ASTM International, Steel, Work hardening, Temperature, Irradiation (Radiation exposure), Neutrons
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
Open the PDF for Alternative Method of RT NDT Determination for Some Reactor Vessel Weld Metals Validated by Fracture Toughness Data in another window
Topics: Fracture toughness, Metals, Reactor vessels, Temperature, Ductility, Weight (Mass), ASME Standards, ASTM International, Embrittlement, Fluence (Radiation measurement)
Journal Articles

Study on Life Extension of Aged RPV Material Based on Probabilistic Fracture Mechanics: Japanese Round Robin

G. Yagawa, S. Yoshimura, N. Handa, T. Uno, K. Watashi, T. Fujioka, H. Ueda, M. Uno, K. Hojo, S. Ueda
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. February 1995, 117(1): 7–13.
https://doi.org/10.1115/1.2842095
Published Online: February 1, 1995
View Article titled, Study on Life Extension of Aged RPV Material Based on Probabilistic Fracture Mechanics: Japanese Round Robin
Open the PDF for Study on Life Extension of Aged RPV Material Based on Probabilistic Fracture Mechanics: Japanese Round Robin in another window
Topics: Fracture mechanics, Life extension, Failure, Probability, Fracture toughness, Pressurized water reactors, Surface cracks, ASME Standards, Bending (Stress), Computer software
Journal Articles

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

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 Article titled, Verification of Warm Prestressing Effect Under a Pressurized Thermal Shock (PTS) Event
Open the PDF for Verification of Warm Prestressing Effect Under a Pressurized Thermal Shock (PTS) Event in another window
Topics: Cooling, Electromagnetic scattering, Embrittlement, Fracture (Materials), Fracture (Process), Fracture toughness, Irradiation (Radiation exposure), Neutrons, Pressurized water reactors, Reactor vessels
Journal Articles

Use of Fundamental Modeling of Environmental Cracking for Improved Design and Lifetime Evaluation

P. L. Andresen, F. P. Ford
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. November 1993, 115(4): 353–358.
https://doi.org/10.1115/1.2929541
Published Online: November 1, 1993
View Article titled, Use of Fundamental Modeling of Environmental Cracking for Improved Design and Lifetime Evaluation
Open the PDF for Use of Fundamental Modeling of Environmental Cracking for Improved Design and Lifetime Evaluation in another window
Topics: Cracking (Materials), Design, Fracture (Process), Modeling, Energy industry, Fracture (Materials), Hot water, Irradiation (Radiation exposure), Nickel alloys, Stainless steel
Journal Articles

Heavy-Section Steel Technology Program: Fracture Issues (Survey Paper)

W. E. Pennell
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research Papers
J. Pressure Vessel Technol. August 1992, 114(3): 255–264.
https://doi.org/10.1115/1.2929039
Published Online: August 1, 1992
View Article titled, Heavy-Section Steel Technology Program: Fracture Issues (Survey Paper)
Open the PDF for Heavy-Section Steel Technology Program: Fracture Issues (Survey Paper) in another window
Topics: Fracture (Materials), Fracture (Process), Steel, Reactor vessels, Fracture mechanics, Vessels, Cladding systems (Building), Crack propagation, Fracture toughness, Irradiation (Radiation exposure)