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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
Proceedings Papers

Effect of Coolant Water Temperature of ECCS on Failure Probability of RPV

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Jinya Katsuyama, Koichi Masaki, Kai Lu, Tadashi Watanabe, Yinsheng Li
Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A059, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93967
https://doi.org/10.1115/PVP2019-93967
View Paper titled, Effect of Coolant Water Temperature of ECCS on Failure Probability of RPV
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Topics: Coolants, Emergency core cooling systems, Failure, Fracture mechanics, Probability, Thermal shock, Water temperature, Temperature, Pressure, Pressurized water reactors
Proceedings Papers

Loading Condition Evaluation for Structural Integrity Assessment of RPV due to PTS Event Based on Three-Dimensional Thermal-Hydraulics and Structural Analyses

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Shumpei Uno, Jinya Katsuyama, Tadashi Watanabe, Yinsheng Li
Proc. ASME. PVP2016, Volume 1B: Codes and Standards, V01BT01A039, July 17–21, 2016
Publisher: American Society of Mechanical Engineers
Paper No: PVP2016-63443
https://doi.org/10.1115/PVP2016-63443
View Paper titled, Loading Condition Evaluation for Structural Integrity Assessment of RPV due to PTS Event Based on Three-Dimensional Thermal-Hydraulics and Structural Analyses
Open the PDF for Loading Condition Evaluation for Structural Integrity Assessment of RPV due to PTS Event Based on Three-Dimensional Thermal-Hydraulics and Structural Analyses in another window
Topics: Structural analysis, Thermal hydraulics, Coolants, Water, Heat transfer coefficients, Cladding systems (Building), Heat treating (Metalworking), Overlays (Materials engineering), Pressurized water reactors, Reactor vessels
Proceedings Papers

Study on Structural Integrity Assessment of Reactor Pressure Vessel Based on Three-Dimensional Thermal-Hydraulics and Structural Analyses

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Jinya Katsuyama, Genshichiro Katsumata, Kunio Onizawa, Tadashi Watanabe, Yutaka Nishiyama
Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A097, July 20–24, 2014
Publisher: American Society of Mechanical Engineers
Paper No: PVP2014-28645
https://doi.org/10.1115/PVP2014-28645
View Paper titled, Study on Structural Integrity Assessment of Reactor Pressure Vessel Based on Three-Dimensional Thermal-Hydraulics and Structural Analyses
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Topics: Reactor vessels, Structural analysis, Thermal hydraulics, Coolants, Water, Crack propagation, Fracture (Materials), Heat transfer coefficients, Pressure vessels, Pressurized water reactors
Proceedings Papers

Simulation of Oscillating Free Interface Behavior by Using OpenFOAM

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Qingyun Zeng, Jiejin Cai, Tadashi Watanabe
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A046, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15586
https://doi.org/10.1115/ICONE21-15586
View Paper titled, Simulation of Oscillating Free Interface Behavior by Using OpenFOAM
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Topics: Simulation, Bubbles, Two-phase flow, Oscillations, Pressure
Proceedings Papers

RELAP5/MOD3 Code Verification Through PWR Pressure Vessel Small Break LOCA Tests in OECD/NEA ROSA Project

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Hideo Nakamura, Tadashi Watanabe, Takeshi Takeda, Hideaki Asaka, Masaya Kondo, Yu Maruyama, Iwao Ohtsu, Mitsuhiro Suzuki
Proc. ASME. ICONE16, Volume 3: Thermal Hydraulics; Instrumentation and Controls, 659-668, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48615
https://doi.org/10.1115/ICONE16-48615
View Paper titled, RELAP5/MOD3 Code Verification Through PWR Pressure Vessel Small Break LOCA Tests in OECD/NEA ROSA Project
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Topics: Accidents, Engineering simulation, Light water reactors, Nuclear power, Pressure vessels, Pressurized water reactors, Safety, Simulation, Simulation models, Transients (Dynamics)
Proceedings Papers

Pore-Scale Simulation for Predicting Material Transport Through Porous Media

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Goichi Itoh, Jinya Nakamura, Koji Kono, Tadashi Watanabe, Hirotada Ohashi, Yu Chen, Shinya Nagasaki
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 397-404, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22563
https://doi.org/10.1115/ICONE10-22563
View Paper titled, Pore-Scale Simulation for Predicting Material Transport Through Porous Media
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Topics: Porous materials, Simulation, Computation, Fluid dynamics, Boundary-value problems, Darcy's law, Flow (Dynamics), Geometry, Lattice Boltzmann methods, Pressure gradient
Proceedings Papers

Numerical Simulation of the Interfacial Growth of the Stratified Wavy Two-Phase Flow in the Horizontal Rectangular Channel

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Ken-ichi Ebihara, Tadashi Watanabe
Proc. ASME. IMECE2004, Fluids Engineering, 503-511, November 13–19, 2004
Publisher: American Society of Mechanical Engineers
Paper No: IMECE2004-59679
https://doi.org/10.1115/IMECE2004-59679
View Paper titled, Numerical Simulation of the Interfacial Growth of the Stratified Wavy Two-Phase Flow in the Horizontal Rectangular Channel
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Topics: Computer simulation, Two-phase flow, Flow (Dynamics), Waves, Dimensionless numbers, Nuclear reactors, Numerical analysis, Computation, Design, Engineering simulation