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Takashi Onizawa
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Proceedings Papers

Evaluation of the Japanese Fatigue Test Data in Gr.91 for Elevated Temperature Design

Masanori Ando, Kodai Toyota, Ryuta Hashidate, Takashi Onizawa
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A017, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-60773
https://doi.org/10.1115/PVP2021-60773
View Paper titled, Evaluation of the Japanese Fatigue Test Data in Gr.91 for Elevated Temperature Design
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Topics: Design, Fatigue testing, Temperature
Proceedings Papers

Proposal of Simulation Material Test Technique for Clarifying the Structure Failure Mechanisms Under Excessive Seismic Loads

Ryuta Hashidate, Shoichi Kato, Takashi Onizawa, Takashi Wakai, Naoto Kasahara
Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A029, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61866
https://doi.org/10.1115/PVP2021-61866
View Paper titled, Proposal of Simulation Material Test Technique for Clarifying the Structure Failure Mechanisms Under Excessive Seismic Loads
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Topics: Constitutive equations, Failure mechanisms, Lead alloys, Simulation, Stress
Proceedings Papers

Proposal of Simulation Materials Test Technique and Their Constitutive Equations for Structural Tests and Analyses Simulating Severe Accident Conditions

Ryuta Hashidate, Shoichi Kato, Takashi Onizawa, Takashi Wakai, Naoto Kasahara
Proc. ASME. PVP2020, Volume 3: Design and Analysis, V003T03A041, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21397
https://doi.org/10.1115/PVP2020-21397
View Paper titled, Proposal of Simulation Materials Test Technique and Their Constitutive Equations for Structural Tests and Analyses Simulating Severe Accident Conditions
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Topics: Accidents, Constitutive equations, Lead alloys, Simulation
Proceedings Papers

A Proposal of Inelastic Constitutive Equations of Lead Alloys Used for Structural Tests Simulating Severe Accident Conditions

Ryuta Hashidate, Takashi Onizawa, Takashi Wakai, Naoto Kasahara
Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A040, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93820
https://doi.org/10.1115/PVP2019-93820
View Paper titled, A Proposal of Inelastic Constitutive Equations of Lead Alloys Used for Structural Tests Simulating Severe Accident Conditions
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Topics: Accidents, Constitutive equations, Lead alloys
Proceedings Papers

The Formulation of Material Characteristics of Austenitic Stainless Steels at Extremely High Temperature

Kenta Shimomura, Takashi Onizawa, Shoichi Kato, Masanori Ando, Takashi Wakai
Proc. ASME. PVP2017, Volume 3B: Design and Analysis, V03BT03A006, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65666
https://doi.org/10.1115/PVP2017-65666
View Paper titled, The Formulation of Material Characteristics of Austenitic Stainless Steels at Extremely High Temperature
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Topics: High temperature, Stainless steel, Accidents, Nuclear power stations, Creep, Numerical analysis, Safety, Finite element analysis, Finite element methods, Fukushima nuclear disaster, Japan, 2011
Journal Articles

The Welded Joint Strength Reduction Factors of Modified 9Cr–1Mo Steel for the Advanced Loop-Type Sodium Cooled Fast Reactor

Takuya Yamashita, Takashi Wakai, Takashi Onizawa, Kenichiro Satoh, Kenji Yamamoto
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. December 2016, 138(6): 061403.
Paper No: PVT-15-1260
https://doi.org/10.1115/1.4034017
Published Online: September 2, 2016
View Article titled, The Welded Joint Strength Reduction Factors of Modified 9Cr–1Mo Steel for the Advanced Loop-Type Sodium Cooled Fast Reactor
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Topics: Base metals, Creep, Rupture, Sodium fast reactors, Steel, Stress, Welded joints, Temperature, Design
Proceedings Papers

Material Strength Evaluation for 60 Years Design in Japanese Sodium Fast Reactor

Yuji Nagae, Takashi Onizawa, Shigeru Takaya, Takuya Yamashita
Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A063, July 20–24, 2014
Publisher: American Society of Mechanical Engineers
Paper No: PVP2014-28689
https://doi.org/10.1115/PVP2014-28689
View Paper titled, Material Strength Evaluation for 60 Years Design in Japanese Sodium Fast Reactor
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Topics: Design, Sodium fast reactors, Strength (Materials), Steel, Stress, Temperature, Boilers, Forgings (Products), Fracture (Materials), Fracture (Process)
Proceedings Papers

Development of Structural Codes for JSFR Based on the System Based Code Concept

Tai Asayama, Takashi Wakai, Masanori Ando, Satoshi Okajima, Yuji Nagae, Shigeru Takaya, Takashi Onizawa, Kazuyuki Tsukimori, Masaki Morishita
Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A064, July 20–24, 2014
Publisher: American Society of Mechanical Engineers
Paper No: PVP2014-28853
https://doi.org/10.1115/PVP2014-28853
View Paper titled, Development of Structural Codes for JSFR Based on the System Based Code Concept
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Topics: Construction, Design, Fast neutron reactors, Fitness-for-service, Industrial research, Japan Society of Mechanical Engineers, Leak-before-break, Reliability, Sodium fast reactors, Welding
Proceedings Papers

Development of Separation Technique of Sodium Nitrate From Low-Level Radioactive Liquid Waste Using Electrodialysis With Selective Ion-Exchange Membranes

Keita Irisawa, Akinori Nakagawa, Takashi Onizawa, Takafumi Kogawara, Keiji Hanada, Yoshihiro Meguro
Proc. ASME. ICEM2013, Volume 1: Low/Intermediate-Level Radioactive Waste Management; Spent Fuel, Fissile Material, Transuranic and High-Level Radioactive Waste Management, V001T01A019, September 8–12, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2013-96104
https://doi.org/10.1115/ICEM2013-96104
View Paper titled, Development of Separation Technique of Sodium Nitrate From Low-Level Radioactive Liquid Waste Using Electrodialysis With Selective Ion-Exchange Membranes
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Topics: Ion exchange, Membranes, Separation (Technology), Sodium, Ions, Temperature
Proceedings Papers

A Study for Proposal of Welded Joint Strength Reduction Factors of Modified 9Cr-1Mo Steel for Japan Sodium Cooled Fast Reactor (JSFR)

Takashi Wakai, Takashi Onizawa, Takehiko Kato, Shingo Date, Koichi Kikuchi, Kenichiro Satoh
Proc. ASME. PVP2013, Volume 3: Design and Analysis, V003T03A105, July 14–18, 2013
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-97091
https://doi.org/10.1115/PVP2013-97091
View Paper titled, A Study for Proposal of Welded Joint Strength Reduction Factors of Modified 9Cr-1Mo Steel for Japan Sodium Cooled Fast Reactor (JSFR)
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Topics: Sodium fast reactors, Steel, Welded joints, Creep, Rupture, Stress, Base metals, Design, Temperature, Damage
Proceedings Papers

Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (2) Development of the Material Strength Standard of 316FR Stainless Steel

Takashi Onizawa, Yuji Nagae, Shigeru Takaya, Tai Asayama
Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A034, July 14–18, 2013
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-97608
https://doi.org/10.1115/PVP2013-97608
View Paper titled, Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (2) Development of the Material Strength Standard of 316FR Stainless Steel
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Topics: Construction, Design, Fast neutron reactors, JSME Standards, Stainless steel, Strength (Materials), Creep, Irradiation (Radiation exposure), Japan Society of Mechanical Engineers, Low cycle fatigue
Proceedings Papers

Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (3) Development of the Material Strength Standard of Modified 9Cr-1Mo Steel

Takashi Onizawa, Yuji Nagae, Shigeru Takaya, Tai Asayama
Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A036, July 14–18, 2013
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-97611
https://doi.org/10.1115/PVP2013-97611
View Paper titled, Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (3) Development of the Material Strength Standard of Modified 9Cr-1Mo Steel
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Topics: Construction, Design, Fast neutron reactors, JSME Standards, Steel, Strength (Materials), Creep, Boilers, Circuits, Coolants
Proceedings Papers

Creep Strength Evaluation of Welded Joint Made of Modified 9Cr-1Mo Steel for Japanese Sodium Cooled Fast Reactor (JSFR)

Takashi Wakai, Yuji Nagae, Takashi Onizawa, Satoshi Obara, Yang Xu, Tomomi Ohtani, Shingo Date, Tai Asayama
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 3, 475-483, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-26014
https://doi.org/10.1115/PVP2010-26014
View Paper titled, Creep Strength Evaluation of Welded Joint Made of Modified 9Cr-1Mo Steel for Japanese Sodium Cooled Fast Reactor (JSFR)
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Topics: Creep, Sodium fast reactors, Steel, Welded joints, Stress, Pipes, Design, Rupture, Circuits, Damage
Proceedings Papers

Development of a Material Strength Standard for Japanese Demonstration Fast Breeder Reactor

Takashi Onizawa, Yuji Nagae, Takashi Wakai, Tai Asayama
Proc. ASME. PVP2009, Volume 1: Codes and Standards, 727-734, July 26–30, 2009
Publisher: American Society of Mechanical Engineers
Paper No: PVP2009-77984
https://doi.org/10.1115/PVP2009-77984
View Paper titled, Development of a Material Strength Standard for Japanese Demonstration Fast Breeder Reactor
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Topics: Breeder reactors, Strength (Materials), Design, Steel, Boilers, Engineering standards, Japan Society of Mechanical Engineers, ASTM International, Circuits, Construction