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Makoto Udagawa
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Journal Articles

Development of Stress Intensity Factors for Cracks With Large Aspect Ratios in Pipes and Plates

Yinsheng Li, Kunio Hasegawa, Makoto Udagawa
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2017, 139(2): 021202.
Paper No: PVT-16-1004
https://doi.org/10.1115/1.4034286
Published Online: September 27, 2016
View Article titled, Development of Stress Intensity Factors for Cracks With Large Aspect Ratios in Pipes and Plates
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Topics: Fracture (Materials), Pipes, Plates (structures), Stress
Proceedings Papers

Development of J-Integral Solutions for Semi-Elliptical Circumferential Cracked Pipes Subjected to Internal Pressure and Bending Moment

Makoto Udagawa, Jinya Katsuyama, Yoshihito Yamaguchi, Yinsheng Li, Kunio Onizawa
Proc. ASME. PVP2015, Volume 6A: Materials and Fabrication, V06AT06A023, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45763
https://doi.org/10.1115/PVP2015-45763
View Paper titled, Development of J-Integral Solutions for Semi-Elliptical Circumferential Cracked Pipes Subjected to Internal Pressure and Bending Moment
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Topics: Pipes, Pressure, Finite element analysis, Fracture (Materials), Surface cracks, Piping systems, Dimensions, Failure, Fracture mechanics, Materials properties
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
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 Article titled, 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
Proceedings Papers

Improvement of Probabilistic Fracture Mechanics Analysis Code for Reactor Piping Considering Large Earthquakes

Yoshihito Yamaguchi, Jinya Katsuyama, Makoto Udagawa, Kunio Onizawa, Yutaka Nishiyama, Yinsheng Li
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T03A022, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30643
https://doi.org/10.1115/ICONE22-30643
View Paper titled, Improvement of Probabilistic Fracture Mechanics Analysis Code for Reactor Piping Considering Large Earthquakes
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Topics: Earthquakes, Fracture mechanics, Pipes, Failure, Fracture (Materials), Probability, Sensitivity analysis, Evaluation methods
Proceedings Papers

SCC Assessment Based on Probability Fracture Mechanics Considering SCC Initiation and Propagation Under Residual Stress Fields Generated by Machining and Welding Process of Pipes

Masahito Mochizuki, Ryohei Ihara, Jinya Katsuyama, Makoto Udagawa
Proc. ASME. PVP2013, Volume 6A: Materials and Fabrication, V06AT06A025, July 14–18, 2013
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-98156
https://doi.org/10.1115/PVP2013-98156
View Paper titled, SCC Assessment Based on Probability Fracture Mechanics Considering SCC Initiation and Propagation Under Residual Stress Fields Generated by Machining and Welding Process of Pipes
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Topics: Fracture mechanics, Machining, Pipes, Probability, Stress, Welding, Butt welding, Stress concentration, Fracture (Materials), Finite element methods
Proceedings Papers

Fracture Toughness Evaluation of Reactor Pressure Vessel Steels by Master Curve Method Using Mini-CT Specimens

Tohru Tobita, Yutaka Nishiyama, Takuyo Ohtsu, Makoto Udagawa, Jinya Katsuyama, Kunio Onizawa
Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A043, July 14–18, 2013
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-97897
https://doi.org/10.1115/PVP2013-97897
View Paper titled, Fracture Toughness Evaluation of Reactor Pressure Vessel Steels by Master Curve Method Using Mini-CT Specimens
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Topics: Fracture toughness, Reactor vessels, Steel, ASTM International, Brittleness, Phase transition temperature, Shapes, Temperature
Journal Articles

Assessment of Residual Stress Due to Overlay-Welded Cladding and Structural Integrity of a Reactor Pressure Vessel

Jinya Katsuyama, Hiroyuki Nishikawa, Makoto Udagawa, Mitsuyuki Nakamura, Kunio Onizawa
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. October 2013, 135(5): 051402.
Paper No: PVT-12-1103
https://doi.org/10.1115/1.4024617
Published Online: September 16, 2013
View Article titled, Assessment of Residual Stress Due to Overlay-Welded Cladding and Structural Integrity of a Reactor Pressure Vessel
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Topics: Cladding systems (Building), Overlays (Materials engineering), Stress, Welding, Finite element methods, Finite element model
Proceedings Papers

Assessments of Residual Stress Due to Weld-Overlay Cladding and Structural Integrity of Reactor Pressure Vessel

Jinya Katsuyama, Hiroyuki Nishikawa, Makoto Udagawa, Mitsuyuki Nakamura, Kunio Onizawa
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B, 1369-1375, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25541
https://doi.org/10.1115/PVP2010-25541
View Paper titled, Assessments of Residual Stress Due to Weld-Overlay Cladding and Structural Integrity of Reactor Pressure Vessel
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Topics: Cladding systems (Building), Overlays (Materials engineering), Reactor vessels, Stress, Heat, Phase transitions, Stress concentration, Alloy steel, Corrosion, Creep
Proceedings Papers

Study on PWSCC Behaviors at Nickel-Based Alloy Welds Based on Weld Residual Stress Analysis and Probabilistic Fracture Mechanics

Makoto Udagawa, Jinya Katsuyama, Kunio Onizawa
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 1, 521-529, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-26028
https://doi.org/10.1115/PVP2010-26028
View Paper titled, Study on PWSCC Behaviors at Nickel-Based Alloy Welds Based on Weld Residual Stress Analysis and Probabilistic Fracture Mechanics
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Topics: Alloys, Fracture mechanics, Nickel, Stress analysis (Engineering), Welded joints, Fracture (Materials), Stress, Stress corrosion cracking, Boiling water reactors, Electromagnetic scattering
Proceedings Papers

Effects of Residual Stress by Weld Overlay Cladding and PWHT on the Structural Integrity of RPV During PTS

Makoto Udagawa, Jinya Katsuyama, Kunio Onizawa
Proc. ASME. PVP2007, Volume 6: Materials and Fabrication, 957-963, July 22–26, 2007
Publisher: American Society of Mechanical Engineers
Paper No: PVP2007-26556
https://doi.org/10.1115/PVP2007-26556
View Paper titled, Effects of Residual Stress by Weld Overlay Cladding and PWHT on the Structural Integrity of RPV During PTS
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Topics: Cladding systems (Building), Overlays (Materials engineering), Stress, Accidents, Coolants, Temperature, Computer simulation, Creep, Evaluation methods, Finite element methods
Proceedings Papers

Study on Estimation Method for Seismic Safety Margin of 3D Piping System With Degradation: Establishing Elasto-Plastic Analysis Model

Akira Mikami, Makoto Udagawa, Hajime Takada
Proc. ASME. PVP2004, High Pressure Technology: Innovations and Advances in High Pressure Technology; 12th Annual ASME/PVPD 2004 Student Paper Competition, 125-134, July 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: PVP2004-2287
https://doi.org/10.1115/PVP2004-2287
View Paper titled, Study on Estimation Method for Seismic Safety Margin of 3D Piping System With Degradation: Establishing Elasto-Plastic Analysis Model
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Topics: Piping systems, Safety, Displacement, Dynamic analysis, Pipes