Search Results | J. Pressure Vessel Technol.

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Journal Articles

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

Ahmadreza Farrokhnia, Andrey P. Jivkov, Graham Hall, Paul Mummery

J. Pressure Vessel Technol. June 2022, 144(3): 031502.

Paper No: PVT-20-1195

DOI: https://doi.org/10.1115/1.4053478

Published Online: February 10, 2022

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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

J. Pressure Vessel Technol. October 2021, 143(5): 051502.

Paper No: PVT-20-1142

DOI: https://doi.org/10.1115/1.4050317

Published Online: March 22, 2021

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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

J. Pressure Vessel Technol. August 2021, 143(4): 041501.

Paper No: PVT-18-1049

DOI: https://doi.org/10.1115/1.4049693

Published Online: February 11, 2021

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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

J. Pressure Vessel Technol. April 2021, 143(2): 021505.

Paper No: PVT-20-1061

DOI: https://doi.org/10.1115/1.4048103

Published Online: October 5, 2020

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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

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

J. Pressure Vessel Technol. April 2021, 143(2): 021202.

Paper No: PVT-19-1261

DOI: https://doi.org/10.1115/1.4047878

Published Online: September 15, 2020

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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

J. Pressure Vessel Technol. April 2021, 143(2): 021201.

Paper No: PVT-19-1260

DOI: https://doi.org/10.1115/1.4047879

Published Online: September 15, 2020

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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

J. Pressure Vessel Technol. April 2020, 142(2): 021205.

Paper No: PVT-19-1082

DOI: https://doi.org/10.1115/1.4045874

Published Online: February 24, 2020

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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

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

J. Pressure Vessel Technol. June 2016, 138(3): 031202.

Paper No: PVT-15-1089

DOI: https://doi.org/10.1115/1.4032110

Published Online: February 8, 2016

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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

J. Pressure Vessel Technol. June 2012, 134(3): 031402.

DOI: https://doi.org/10.1115/1.4005868

Published Online: May 18, 2012

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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

J. Pressure Vessel Technol. June 2012, 134(3): 031002.

DOI: https://doi.org/10.1115/1.4006580

Published Online: May 18, 2012

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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

J. Pressure Vessel Technol. December 2010, 132(6): 064001.

DOI: https://doi.org/10.1115/1.4001425

Published Online: October 14, 2010

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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

J. Pressure Vessel Technol. February 2001, 123(1): 49–57.

DOI: https://doi.org/10.1115/1.1338119

Published Online: October 27, 2000

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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

J. Pressure Vessel Technol. August 1998, 120(3): 290–296.

DOI: https://doi.org/10.1115/1.2842060

Published Online: August 1, 1998

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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

J. Pressure Vessel Technol. May 1997, 119(2): 150–156.

DOI: https://doi.org/10.1115/1.2842276

Published Online: May 1, 1997

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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

J. Pressure Vessel Technol. November 1995, 117(4): 341–345.

DOI: https://doi.org/10.1115/1.2842133

Published Online: November 1, 1995

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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

J. Pressure Vessel Technol. November 1995, 117(4): 378–382.

DOI: https://doi.org/10.1115/1.2842139

Published Online: November 1, 1995

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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

J. Pressure Vessel Technol. February 1995, 117(1): 7–13.

DOI: https://doi.org/10.1115/1.2842095

Published Online: February 1, 1995

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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

J. Pressure Vessel Technol. August 1994, 116(3): 267–273.

DOI: https://doi.org/10.1115/1.2929586

Published Online: August 1, 1994

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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

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

P. L. Andresen, F. P. Ford

J. Pressure Vessel Technol. November 1993, 115(4): 353–358.

DOI: https://doi.org/10.1115/1.2929541

Published Online: November 1, 1993

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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

J. Pressure Vessel Technol. August 1992, 114(3): 255–264.

DOI: https://doi.org/10.1115/1.2929039

Published Online: August 1, 1992

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Topics: Fracture (Materials), Fracture (Process), Steel, Reactor vessels, Fracture mechanics, Vessels, Cladding systems (Building), Crack propagation, Fracture toughness, Irradiation (Radiation exposure)

Journal citation

NARROW

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

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

Verification of Probabilistic Fracture Mechanics Analysis Code for Reactor Pressure Vessel

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

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

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

Guideline on Probabilistic Fracture Mechanics Analysis for Japanese Reactor Pressure Vessels

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

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

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

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

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

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

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

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

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

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

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

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

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

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