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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

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

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

J. Pressure Vessel Technol. October 2018, 140(5): 051302.

Paper No: PVT-17-1134

DOI: https://doi.org/10.1115/1.4040698

Published Online: August 22, 2018

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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

J. Pressure Vessel Technol. October 2018, 140(5): 051402.

Paper No: PVT-18-1039

DOI: https://doi.org/10.1115/1.4040642

Published Online: August 2, 2018

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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

J. Pressure Vessel Technol. August 2016, 138(4): 040802.

Paper No: PVT-15-1166

DOI: https://doi.org/10.1115/1.4031910

Published Online: April 28, 2016

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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

J. Pressure Vessel Technol. August 2016, 138(4): 040801.

Paper No: PVT-15-1130

DOI: https://doi.org/10.1115/1.4031909

Published Online: April 28, 2016

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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

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

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

Koichi Masaki, Jinya Katsuyama, Kunio Onizawa

J. Pressure Vessel Technol. February 2014, 136(1): 011208.

Paper No: PVT-13-1034

DOI: https://doi.org/10.1115/1.4025615

Published Online: November 27, 2013

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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

J. Pressure Vessel Technol. August 2013, 135(4): 041205.

Paper No: PVT-12-1086

DOI: https://doi.org/10.1115/1.4024446

Published Online: June 11, 2013

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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

J. Pressure Vessel Technol. February 2013, 135(1): 011206.

Paper No: PVT-12-1003

DOI: https://doi.org/10.1115/1.4007292

Published Online: December 17, 2012

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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

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

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

J. Pressure Vessel Technol. February 2010, 132(1): 011502.

DOI: https://doi.org/10.1115/1.4000344

Published Online: January 4, 2010

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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

J. Pressure Vessel Technol. August 2004, 126(3): 284–292.

DOI: https://doi.org/10.1115/1.1763932

Published Online: August 18, 2004

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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

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

Residual Stresses in Steel and Zirconium Weldments

J. H. Root, C. E. Coleman, J. W. Bowden, M. Hayashi

J. Pressure Vessel Technol. May 1997, 119(2): 137–141.

DOI: https://doi.org/10.1115/1.2842274

Published Online: May 1, 1997

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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

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 citation

NARROW

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

Guideline on Probabilistic Fracture Mechanics Analysis for Japanese Reactor Pressure Vessels

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

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

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

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

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

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

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

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

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

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

Surface and Bulk Residual Stress in Ti6Al4V Welded Aerospace Tanks

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

Residual Stresses in Steel and Zirconium Weldments

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

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

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