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Proceedings Papers

Ductile Tearing Prediction of Ferritic Pipe Material by GTN Model for ATLAS+ European Project

Kiminobu Hojo, Takatoshi Hirota, Naoki Ogawa, Satoshi Kumagai

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A047, August 3, 2020

Paper No: PVP2020-21645

DOI: https://doi.org/10.1115/PVP2020-21645

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Topics: Pipes, Fracture (Materials), Fracture (Process), Coolants, Ductile fracture, Fracture mechanics, Nuclear reactors, Pressure, Simulation, Stress

Proceedings Papers

Investigation of Temperature Dependence of Weibull Parameters of the Beremin Model in Ductile-Brittle Transition Temperature Region

Kiminobu Hojo, Naoki Ogawa, Kentaro Yoshimoto, Takatoshi Hirota, Yasuto Nagoshi

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A014, August 3, 2020

Paper No: PVP2020-21651

DOI: https://doi.org/10.1115/PVP2020-21651

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Topics: Ductile-brittle transition, Temperature, Temperature effects, Alloy steel, Fracture (Materials), Fracture (Process), Brittle fracture, Carbon steel, Ductile fracture, Electromagnetic scattering

Proceedings Papers

Fracture Analysis of Ductile-Brittle Transition Temperature Region Considering Specimens With Different Constraints

Kiminobu Hojo, Takatoshi Hirota, Naoki Ogawa, Kentaro Yoshimoto, Yasuto Nagoshi, Shinichi Kawabata

Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A057, July 15–20, 2018

Paper No: PVP2018-84385

DOI: https://doi.org/10.1115/PVP2018-84385

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Topics: Ductile-brittle transition, Fracture (Materials), Fracture (Process), Temperature, Electromagnetic scattering, Flat plates, Brittleness, Damage mechanics, Ductile fracture, Evaluation methods

Proceedings Papers

Mode I Ductile Crack Growth of 1TCT Specimen Under Large Cyclic Loading: Part II

Kiminobu Hojo, Shinichi Kawabata, Naoki Ogawa

Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A044, July 15–20, 2018

Paper No: PVP2018-84383

DOI: https://doi.org/10.1115/PVP2018-84383

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Topics: Ductile fracture, Stress, Fitness-for-service, Fracture (Materials), Hardening, Japan Society of Mechanical Engineers, Compression, Computational methods, Cycles, Welding

Proceedings Papers

Study on Evaluation Procedure for Calculating the Stress Intensity Factor of Flaws Beneath RPV Cladding During Pressurised Thermal Shock Events by FE Analysis

Hiroyuki Sakamoto, Takatoshi Hirota, Naoki Ogawa

Proc. ASME. PVP2016, Volume 1B: Codes and Standards, V01BT01A038, July 17–21, 2016

Paper No: PVP2016-63210

DOI: https://doi.org/10.1115/PVP2016-63210

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Topics: Cladding systems (Building), Finite element analysis, Stress, Thermal shock, Welding, Alloys, Steel, Cooling, Fracture (Materials), Reactor vessels

Proceedings Papers

Inherent Strain Method for Residual Stress Measurement and Welding Distortion Prediction

Ninshu Ma, Keiji Nakacho, Takahiko Ohta, Naoki Ogawa, Akira Maekawa, Hui Huang, Hidekazu Murakawa

Proc. ASME. OMAE2016, Volume 9: Prof. Norman Jones Honoring Symposium on Impact Engineering; Prof. Yukio Ueda Honoring Symposium on Idealized Nonlinear Mechanics for Welding and Strength of Structures, V009T13A001, June 19–24, 2016

Paper No: OMAE2016-54184

DOI: https://doi.org/10.1115/OMAE2016-54184

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Topics: Stress, Welding, Residual stresses, Welded joints, Deformation, Jigs and fixtures, Neutron diffraction, Pipes, Plates (structures)

Proceedings Papers

Proposal for Update on Evaluation Procedure for Reactor Pressure Vessels Against Pressurized Thermal Shock Events in Japan

Takatoshi Hirota, Hiroyuki Sakamoto, Naoki Ogawa

Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A093, July 20–24, 2014

Paper No: PVP2014-28392

DOI: https://doi.org/10.1115/PVP2014-28392

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Topics: Reactor vessels, Thermal shock, Fracture toughness, Fracture mechanics, In-service inspection, Nuclear power stations, Pressurized water reactors

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

Proceedings Papers

Residual Stress Evaluation of Dissimilar Weld Joint Using Mock-Up Models of Bottom Mounted Instrument Nozzle

Naoki Ogawa, Kiminobu Hojo, Hiroaki Shirako, Takehiko Sera

Proc. ASME. PVP2013, Volume 6B: Materials and Fabrication, V06BT06A082, July 14–18, 2013

Paper No: PVP2013-97866

DOI: https://doi.org/10.1115/PVP2013-97866

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Topics: Instrumentation, Nozzles, Stress, Manufacturing, Accuracy and precision, Errors, Finite element analysis, Geometry, Hoop stress, Pressurized water reactors

Proceedings Papers

Evaluation on Constraint Effect of Reactor Pressure Vessel Under Pressurized Thermal Shock

Naoki Ogawa, Kentaro Yoshimoto, Takatoshi Hirota, Shohei Sakaguchi, Toru Oumaya

Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A056, July 14–18, 2013

Paper No: PVP2013-97566

DOI: https://doi.org/10.1115/PVP2013-97566

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Topics: Reactor vessels, Thermal shock, Fracture (Materials), Fracture toughness, Accidents, Stress, Surface cracks, Coolants, Deformation, Finite element analysis

Proceedings Papers

Application of Gurson Model to Ni-Based Alloy Weld Joint Pipe With an Axial or a Circumferential Surface Flaw

Kiminobu Hojo, Naoki Ogawa

Proc. ASME. PVP2012, Volume 1: Codes and Standards, 833-840, July 15–19, 2012

Paper No: PVP2012-78171

DOI: https://doi.org/10.1115/PVP2012-78171

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Topics: Alloys, Pipes, Stress, Fracture (Materials), Temperature, Pressure, Evaluation methods, Geometry, High temperature, Welding

Proceedings Papers

Coalescence Phenomena of Liquid Droplets in a Circular Tube

Masahiro Muraoka, Naoki Ogawa, Hiroshi Matsuda, Jin Kasuya, Kenji Komiya, Ichiro Ueno, Hiroshi Mizoguchi

Proc. ASME. AJK2011, ASME-JSME-KSME 2011 Joint Fluids Engineering Conference: Volume 1, Symposia – Parts A, B, C, and D, 2999-3004, July 24–29, 2011

Paper No: AJK2011-16033

DOI: https://doi.org/10.1115/AJK2011-16033

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Topics: Drops, Particulate matter, Buoyancy, Flow (Dynamics), Fluids, Image processing

Proceedings Papers

Sensitivity Analysis of SCC Crack Extension Simulation

Naoki Ogawa, Kiminobu Hojo, Do-Jun Shim, Kazuo Ogawa

Proc. ASME. PVP2011, Volume 1: Codes and Standards, 1007-1014, July 17–21, 2011

Paper No: PVP2011-57454

DOI: https://doi.org/10.1115/PVP2011-57454

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Topics: Fracture (Materials), Sensitivity analysis, Simulation, Finite element analysis, Finite element methods, Finite element model, Mesh generation, Stress, Stress concentration

Proceedings Papers

Fracture Evaluation of Ni-Based Alloy Weld Joint of Cylindrical Model Subjected to 4-Point Bending or Inner Pressure

Kazuo Ogawa, Kiminobu Hojo, Itaru Muroya, Youichi Iwamoto, Naoki Ogawa

Proc. ASME. PVP2011, Volume 1: Codes and Standards, 863-874, July 17–21, 2011

Paper No: PVP2011-57081

DOI: https://doi.org/10.1115/PVP2011-57081

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Topics: Alloys, Fracture (Materials), Fracture (Process), Pressure, Stress, Pipes, Temperature, Evaluation methods, Flow (Dynamics), High temperature

Proceedings Papers

Sensitivity Analysis of Residual Stress Simulation of Dissimilar Metal Joint of Safe End Nozzle and Key Issues for Standard Procedure to Maintenance Rules

Kiminobu Hojo, Kazuo Ogawa, Naoki Ogawa, Itaru Muroya

Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 1, 929-939, July 18–22, 2010

Paper No: PVP2010-25936

DOI: https://doi.org/10.1115/PVP2010-25936

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Topics: Maintenance, Metals, Nozzles, Sensitivity analysis, Simulation, Stress, Computer simulation, Fracture (Materials), Nuclear power, Safety

Proceedings Papers

Fracture Evaluation Using Limit Analysis for Complex Structure (Pressure Load)

Kiminobu Hojo, Mayumi Ochi, Kazuo Ogawa, Naoki Ogawa

Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 1, 941-952, July 18–22, 2010

Paper No: PVP2010-26114

DOI: https://doi.org/10.1115/PVP2010-26114

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Topics: Fracture (Materials), Fracture (Process), Pressure, Stress, Pipes, Nozzles, Evaluation methods, Failure, Materials properties

Proceedings Papers

Mixing Behaviour of Coalescing Droplets in a Tube

Masahiro Muraoka, Naoki Ogawa, Renpei Fujita, Ichiro Ueno, Hiroshi Mizoguchi

Proc. ASME. InterPACK2009, ASME 2009 InterPACK Conference, Volume 2, 357-361, July 19–23, 2009

Paper No: InterPACK2009-89121

DOI: https://doi.org/10.1115/InterPACK2009-89121

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Topics: Drops, Particulate matter, Flow (Dynamics), Fluids, Geometry

Proceedings Papers

Simplified Stress Intensity Factor Equation for SCC Propagation in the Pipe Welds (Step 2)

Mayumi Ochi, Kiminobu Hojo, Kazuo Ogawa, Naoki Ogawa

Proc. ASME. PVP2009, Volume 3: Design and Analysis, 183-190, July 26–30, 2009

Paper No: PVP2009-78001

DOI: https://doi.org/10.1115/PVP2009-78001

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Topics: Pipes, Stress, Welded joints, Fracture (Materials), Finite element analysis, Nozzles, Shapes, Welding

Proceedings Papers

Residual Stress Evaluation of Dissimilar Weld Joint Using Reactor Vessel Outlet Nozzle Mock-Up Model: Report 2

Naoki Ogawa, Itaru Muroya, Youichi Iwamoto, Kiminobu Hojo, Kazuo Ogawa, Ed Kingston, David J. Smith

Proc. ASME. PVP2009, Volume 6: Materials and Fabrication, Parts A and B, 353-364, July 26–30, 2009

Paper No: PVP2009-77269

DOI: https://doi.org/10.1115/PVP2009-77269

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Topics: Nozzles, Reactor vessels, Stress, Manufacturing, Stress concentration, Alloys, Evaluation methods, Finite element analysis, Hydrostatic testing, Pressurized water reactors

Proceedings Papers

Structural Integrity of Penetration Nozzle of Reactor Pressure Vessel Head of PWR Plant

Kiminobu Hojo, Naoki Ogawa, Yoichi Iwamoto, Kazutoshi Ohoto, Seiji Asada, Hajime Ito, Shinro Hirano

Proc. ASME. PVP2008, Volume 1: Codes and Standards, 17-27, July 27–31, 2008

Paper No: PVP2008-61178

DOI: https://doi.org/10.1115/PVP2008-61178

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Topics: Nozzles, Pressurized water reactors, Reactor vessels, Stress, Fracture (Materials), Brittle fracture, Computational methods, Fatigue cracks, Finite element analysis, Modeling

Journal citation

NARROW

Ductile Tearing Prediction of Ferritic Pipe Material by GTN Model for ATLAS+ European Project

Investigation of Temperature Dependence of Weibull Parameters of the Beremin Model in Ductile-Brittle Transition Temperature Region

Fracture Analysis of Ductile-Brittle Transition Temperature Region Considering Specimens With Different Constraints

Mode I Ductile Crack Growth of 1TCT Specimen Under Large Cyclic Loading: Part II

Study on Evaluation Procedure for Calculating the Stress Intensity Factor of Flaws Beneath RPV Cladding During Pressurised Thermal Shock Events by FE Analysis

Inherent Strain Method for Residual Stress Measurement and Welding Distortion Prediction

Proposal for Update on Evaluation Procedure for Reactor Pressure Vessels Against Pressurized Thermal Shock Events in Japan

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

Residual Stress Evaluation of Dissimilar Weld Joint Using Mock-Up Models of Bottom Mounted Instrument Nozzle

Evaluation on Constraint Effect of Reactor Pressure Vessel Under Pressurized Thermal Shock

Application of Gurson Model to Ni-Based Alloy Weld Joint Pipe With an Axial or a Circumferential Surface Flaw

Coalescence Phenomena of Liquid Droplets in a Circular Tube

Sensitivity Analysis of SCC Crack Extension Simulation

Fracture Evaluation of Ni-Based Alloy Weld Joint of Cylindrical Model Subjected to 4-Point Bending or Inner Pressure

Sensitivity Analysis of Residual Stress Simulation of Dissimilar Metal Joint of Safe End Nozzle and Key Issues for Standard Procedure to Maintenance Rules

Fracture Evaluation Using Limit Analysis for Complex Structure (Pressure Load)

Mixing Behaviour of Coalescing Droplets in a Tube

Simplified Stress Intensity Factor Equation for SCC Propagation in the Pipe Welds (Step 2)

Residual Stress Evaluation of Dissimilar Weld Joint Using Reactor Vessel Outlet Nozzle Mock-Up Model: Report 2

Structural Integrity of Penetration Nozzle of Reactor Pressure Vessel Head of PWR Plant

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