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Journal Articles

Statistical Characteristic of the Transition Temperature Shift for Reactor Pressure Vessel Steel

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Naoki Miura, Tomoki Shinko
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. June 2025, 147(3): 031502.
Paper No: PVT-23-1162
https://doi.org/10.1115/1.4067725
Published Online: February 19, 2025
View Articletitled, Statistical Characteristic of the Transition Temperature Shift for Reactor Pressure Vessel Steel
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Topics: Irradiation (Radiation exposure), Phase transition temperature, Steel, Temperature, Fracture toughness, Reactor vessels
Journal Articles

Statistical Distribution Model of Charpy Absorbed Energy in Transition Temperature Range for Reactor Pressure Vessel Steel

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Naoki Miura, Tomoki Shinko
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. October 2023, 145(5): 051501.
Paper No: PVT-23-1011
https://doi.org/10.1115/1.4062674
Published Online: June 16, 2023
View Articletitled, Statistical Distribution Model of Charpy Absorbed Energy in Transition Temperature Range for Reactor Pressure Vessel Steel
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Topics: Fracture toughness, Notch testing, Phase transition temperature, Reactor vessels, Shapes, Statistical distributions, Steel, Temperature, Weibull distribution, Gaussian distribution
Journal Articles

Fracture Toughness Evaluation of the Heat-Affected Zone Under the Weld Overlay Cladding in Reactor Pressure Vessel Steel

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Yoosung Ha, Tohru Tobita, Hisashi Takamizawa, Jinya Katsuyama
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2023, 145(2): 021501.
Paper No: PVT-22-1083
https://doi.org/10.1115/1.4055626
Published Online: December 2, 2022
View Articletitled, Fracture Toughness Evaluation of the Heat-Affected Zone Under the Weld Overlay Cladding in Reactor Pressure Vessel Steel
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Topics: Base metals, Cladding systems (Building), Fracture toughness, Heat, Steel, Overlays (Materials engineering), Reactor vessels
Journal Articles

Deterministic and Probabilistic Evaluation of Seismic Loads on Reactor Pressure Vessel Internals Including Nonlinear Effects

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Johannes Schmidl, Manuel Pellissetti, Eugen Fuetterer, Roland Hilpert, Andrii Nykyforchyn, Sunay Staeuble-Akcay
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. June 2022, 144(3): 031902.
Paper No: PVT-20-1232
https://doi.org/10.1115/1.4053753
Published Online: March 8, 2022
View Articletitled, Deterministic and Probabilistic Evaluation of Seismic Loads on Reactor Pressure Vessel Internals Including Nonlinear Effects
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Topics: Excitation, Flanges, Stress, Spectra (Spectroscopy), Reactor vessels, Soil
Journal Articles

Constraint Effect on Fracture Behavior of Underclad Crack in Reactor Pressure Vessel

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Masaki Shimodaira, Tohru Tobita, Hisashi Takamizawa, Jinya Katsuyama, Satoshi Hanawa
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. February 2022, 144(1): 011304.
Paper No: PVT-21-1049
https://doi.org/10.1115/1.4051704
Published Online: August 4, 2021
View Articletitled, Constraint Effect on Fracture Behavior of Underclad Crack in Reactor Pressure Vessel
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Topics: Cladding systems (Building), Finite element analysis, Fracture (Materials), Fracture toughness, Reactor vessels, Stress, Surface cracks
Journal Articles

Validation of Monte Carlo Simulation Technique for Calibration of Cleavage Fracture Model Parameters, With the Calibrated Values From Experimental Results for Reactor Pressure Vessel Material 20MnMoNi55 Steel in the Lower Self of Ductile-to-Brittle Transition Region

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K. Bhattacharyya, S. K. Acharyya
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. December 2021, 143(6): 061503.
Paper No: PVT-20-1106
https://doi.org/10.1115/1.4051021
Published Online: May 31, 2021
View Articletitled, Validation of Monte Carlo Simulation Technique for Calibration of Cleavage Fracture Model Parameters, With the Calibrated Values From Experimental Results for Reactor Pressure Vessel Material 20MnMoNi55 Steel in the Lower Self of Ductile-to-Brittle Transition Region
Open the PDF for Validation of Monte Carlo Simulation Technique for Calibration of Cleavage Fracture Model Parameters, With the Calibrated Values From Experimental Results for Reactor Pressure Vessel Material 20MnMoNi55 Steel in the Lower Self of Ductile-to-Brittle Transition Region in another window
Topics: Brittleness, Calibration, Fracture (Materials), Fracture (Process), Simulation, Steel, Stress, Temperature, Reactor vessels, Fracture toughness
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

Effect of Coolant Water Temperature of Emergency Core Cooling System on Failure Probability of Reactor Pressure Vessel

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Kai Lu, Jinya Katsuyama, Koichi Masaki, Tadashi Watanabe, Yinsheng Li
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. June 2021, 143(3): 031704.
Paper No: PVT-20-1128
https://doi.org/10.1115/1.4049048
Published Online: November 18, 2020
View Articletitled, Effect of Coolant Water Temperature of Emergency Core Cooling System on Failure Probability of Reactor Pressure Vessel
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Topics: Coolants, Emergency core cooling systems, Failure, Fracture mechanics, Pressurized water reactors, Probability, Reactor vessels, Water temperature
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

Plasticity Correction on Stress Intensity Factor Evaluation for Underclad Cracks in Reactor Pressure Vessels

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Kai Lu, Jinya Katsuyama, Yinsheng Li
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. October 2020, 142(5): 051501.
Paper No: PVT-18-1079
https://doi.org/10.1115/1.4046977
Published Online: May 22, 2020
View Articletitled, Plasticity Correction on Stress Intensity Factor Evaluation for Underclad Cracks in Reactor Pressure Vessels
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Topics: Finite element analysis, Fracture (Materials), Plasticity, Reactor vessels, Stress, Cladding systems (Building)
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

Evaluation of Fracture Toughness of a SA580 Gr. 3 Reactor Pressure Vessel Using a Bimodal Master Curve Approach

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Jong-Min Kim, Seok-Min Hong, Min-Chul Kim, Bong-Sang Lee
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. December 2019, 141(6): 061403.
Paper No: PVT-18-1235
https://doi.org/10.1115/1.4044263
Published Online: August 2, 2019
View Articletitled, Evaluation of Fracture Toughness of a SA580 Gr. 3 Reactor Pressure Vessel Using a Bimodal Master Curve Approach
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Topics: Fracture toughness, Temperature, Reactor vessels
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

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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 Articletitled, 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
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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

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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 Articletitled, 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

Comparative Study on Reactor Pressure Vessel Failure Behaviors With Various Geometric Discontinuities Under Severe Accident

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Jianwei Zhu, Jianfeng Mao, Shiyi Bao, Lijia Luo, Zengliang Gao
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2017, 139(2): 021214.
Paper No: PVT-16-1051
https://doi.org/10.1115/1.4035697
Published Online: February 3, 2017
View Articletitled, Comparative Study on Reactor Pressure Vessel Failure Behaviors With Various Geometric Discontinuities Under Severe Accident
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Topics: Accidents, Creep, Damage, Failure, Stress, Temperature, Wall thickness, Modeling, Reactor vessels, High temperature
Journal Articles

Investigation on Structural Behaviors of Reactor Pressure Vessel With the Effects of Critical Heat Flux and Internal Pressure

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Jianfeng Mao, Jianwei Zhu, Shiyi Bao, Lijia Luo, Zengliang Gao
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2017, 139(2): 021206.
Paper No: PVT-16-1023
https://doi.org/10.1115/1.4034582
Published Online: September 28, 2016
View Articletitled, Investigation on Structural Behaviors of Reactor Pressure Vessel With the Effects of Critical Heat Flux and Internal Pressure
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Topics: Creep, Damage, Pressure, Stress, Critical heat flux, Reactor vessels
Journal Articles

Probabilistic Pressurized Thermal Shock Analysis for a Reactor Pressure Vessel Considering Plume Cooling Effect

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Guian Qian, V. F. González-Albuixech, Markus Niffenegger, Medhat Sharabi
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. August 2016, 138(4): 041204.
Paper No: PVT-15-1177
https://doi.org/10.1115/1.4032197
Published Online: April 28, 2016
View Articletitled, Probabilistic Pressurized Thermal Shock Analysis for a Reactor Pressure Vessel Considering Plume Cooling Effect
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Topics: Computational fluid dynamics, Cooling, Fracture (Materials), Fracture mechanics, Plumes (Fluid dynamics), Reactor vessels, Thermal shock, Stress, Safety, Probability
Journal Articles

Study on Minimum Wall Thickness Requirement for Seismic Buckling of Reactor Vessel Based on System Based Code Concept

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Shigeru Takaya, Daigo Watanabe, Shinobu Yokoi, Yoshio Kamishima, Kenichi Kurisaka, Tai Asayama
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. October 2015, 137(5): 051802.
Paper No: PVT-14-1003
https://doi.org/10.1115/1.4029322
Published Online: October 1, 2015
View Articletitled, Study on Minimum Wall Thickness Requirement for Seismic Buckling of Reactor Vessel Based on System Based Code Concept
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Topics: Buckling, Design, Earthquakes, Reliability, Stress, Wall thickness, Probability, Statistical distributions, Reactor vessels, Earthquake risk
Journal Articles

Fracture Toughness Evaluation of Reactor Pressure Vessel Steels by Master Curve Method Using Miniature Compact Tension Specimens

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Tohru Tobita, Yutaka Nishiyama, Takuyo Ohtsu, Makoto Udagawa, Jinya Katsuyama, Kunio Onizawa
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. October 2015, 137(5): 051405.
Paper No: PVT-14-1156
https://doi.org/10.1115/1.4029428
Published Online: October 1, 2015
View Articletitled, Fracture Toughness Evaluation of Reactor Pressure Vessel Steels by Master Curve Method Using Miniature Compact Tension Specimens
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Topics: Fracture toughness, Steel, Temperature, Tension, Reactor vessels
Journal Articles

Constraint-Dependent J-R Curves of a Dissimilar Metal Welded Joint for Connecting Pipe-Nozzle of Nuclear Pressure Vessel

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J. Wang, G. Z. Wang, F. Z. Xuan, S. T. Tu
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2015, 137(2): 021405.
Paper No: PVT-13-1182
https://doi.org/10.1115/1.4028993
Published Online: April 1, 2015
View Articletitled, Constraint-Dependent J-R Curves of a Dissimilar Metal Welded Joint for Connecting Pipe-Nozzle of Nuclear Pressure Vessel
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Topics: Fracture (Materials), Stress, Reactor vessels