Search Results | J. Pressure Vessel Technol.

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Journal Articles

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

Yoosung Ha, Tohru Tobita, Hisashi Takamizawa, Jinya Katsuyama

J. Pressure Vessel Technol. April 2023, 145(2): 021501.

Paper No: PVT-22-1083

DOI: https://doi.org/10.1115/1.4055626

Published Online: December 2, 2022

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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

Johannes Schmidl, Manuel Pellissetti, Eugen Fuetterer, Roland Hilpert, Andrii Nykyforchyn, Sunay Staeuble-Akcay

J. Pressure Vessel Technol. June 2022, 144(3): 031902.

Paper No: PVT-20-1232

DOI: https://doi.org/10.1115/1.4053753

Published Online: March 8, 2022

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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

Masaki Shimodaira, Tohru Tobita, Hisashi Takamizawa, Jinya Katsuyama, Satoshi Hanawa

J. Pressure Vessel Technol. February 2022, 144(1): 011304.

Paper No: PVT-21-1049

DOI: https://doi.org/10.1115/1.4051704

Published Online: August 4, 2021

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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

K. Bhattacharyya, S. K. Acharyya

J. Pressure Vessel Technol. December 2021, 143(6): 061503.

Paper No: PVT-20-1106

DOI: https://doi.org/10.1115/1.4051021

Published Online: May 31, 2021

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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

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

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

Kai Lu, Jinya Katsuyama, Koichi Masaki, Tadashi Watanabe, Yinsheng Li

J. Pressure Vessel Technol. June 2021, 143(3): 031704.

Paper No: PVT-20-1128

DOI: https://doi.org/10.1115/1.4049048

Published Online: November 18, 2020

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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

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

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

Kai Lu, Jinya Katsuyama, Yinsheng Li

J. Pressure Vessel Technol. October 2020, 142(5): 051501.

Paper No: PVT-18-1079

DOI: https://doi.org/10.1115/1.4046977

Published Online: May 22, 2020

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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

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

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

Jong-Min Kim, Seok-Min Hong, Min-Chul Kim, Bong-Sang Lee

J. Pressure Vessel Technol. December 2019, 141(6): 061403.

Paper No: PVT-18-1235

DOI: https://doi.org/10.1115/1.4044263

Published Online: August 2, 2019

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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

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

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

Jianwei Zhu, Jianfeng Mao, Shiyi Bao, Lijia Luo, Zengliang Gao

J. Pressure Vessel Technol. April 2017, 139(2): 021214.

Paper No: PVT-16-1051

DOI: https://doi.org/10.1115/1.4035697

Published Online: February 3, 2017

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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

Jianfeng Mao, Jianwei Zhu, Shiyi Bao, Lijia Luo, Zengliang Gao

J. Pressure Vessel Technol. April 2017, 139(2): 021206.

Paper No: PVT-16-1023

DOI: https://doi.org/10.1115/1.4034582

Published Online: September 28, 2016

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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

Guian Qian, V. F. González-Albuixech, Markus Niffenegger, Medhat Sharabi

J. Pressure Vessel Technol. August 2016, 138(4): 041204.

Paper No: PVT-15-1177

DOI: https://doi.org/10.1115/1.4032197

Published Online: April 28, 2016

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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

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

Tohru Tobita, Yutaka Nishiyama, Takuyo Ohtsu, Makoto Udagawa, Jinya Katsuyama, Kunio Onizawa

J. Pressure Vessel Technol. October 2015, 137(5): 051405.

Paper No: PVT-14-1156

DOI: https://doi.org/10.1115/1.4029428

Published Online: October 1, 2015

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Topics: Fracture toughness, Steel, Temperature, Tension, Reactor vessels

Journal Articles

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

Shigeru Takaya, Daigo Watanabe, Shinobu Yokoi, Yoshio Kamishima, Kenichi Kurisaka, Tai Asayama

J. Pressure Vessel Technol. October 2015, 137(5): 051802.

Paper No: PVT-14-1003

DOI: https://doi.org/10.1115/1.4029322

Published Online: October 1, 2015

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Topics: Buckling, Design, Earthquakes, Reliability, Stress, Wall thickness, Probability, Statistical distributions, Reactor vessels, Earthquake risk

Journal Articles

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

J. Wang, G. Z. Wang, F. Z. Xuan, S. T. Tu

J. Pressure Vessel Technol. April 2015, 137(2): 021405.

Paper No: PVT-13-1182

DOI: https://doi.org/10.1115/1.4028993

Published Online: April 1, 2015

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Topics: Fracture (Materials), Stress, Reactor vessels

Journal Articles

Investigation on Constraint Effect of a Reactor Pressure Vessel Subjected to Pressurized Thermal Shocks

Guian Qian, Markus Niffenegger

J. Pressure Vessel Technol. February 2015, 137(1): 011204.

Paper No: PVT-13-1168

DOI: https://doi.org/10.1115/1.4028017

Published Online: September 15, 2014

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Topics: Fracture (Materials), Fracture mechanics, Reactor vessels, Stress, Thermal shock, Transients (Dynamics), Fracture toughness

Journal Articles

Inherent-Strain-Based Theory of Measurement of Three-Dimensional Residual Stress Distribution and Its Application to a Welded Joint in a Reactor Vessel

Keiji Nakacho, Naoki Ogawa, Takahiro Ohta, Michisuke Nayama

J. Pressure Vessel Technol. June 2014, 136(3): 031401.

Paper No: PVT-13-1099

DOI: https://doi.org/10.1115/1.4026496

Published Online: February 27, 2014

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Topics: Errors, Reactor vessels, Stress, Stress concentration, Welded joints, Residual stresses

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Journal citation

NARROW

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

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

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

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

Verification of Probabilistic Fracture Mechanics Analysis Code for Reactor Pressure Vessel

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

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

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

Guideline on Probabilistic Fracture Mechanics Analysis for Japanese Reactor Pressure Vessels

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

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

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

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

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

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

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

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

Investigation on Constraint Effect of a Reactor Pressure Vessel Subjected to Pressurized Thermal Shocks

Inherent-Strain-Based Theory of Measurement of Three-Dimensional Residual Stress Distribution and Its Application to a Welded Joint in a Reactor Vessel

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