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Takuya Yamashita
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Proceedings Papers

MPS Method Simulation for Estimating Fuel Debris Distributions Under the Damaged Reactor Pressure Vessel of 1F Unit-2

Yamato Bando, Akifumi Yamaji, Takuya Yamashita
Proc. ASME. ICEM2023, ASME 2023 International Conference on Environmental Remediation and Radioactive Waste Management, V001T03A004, October 3–6, 2023
Publisher: American Society of Mechanical Engineers
Paper No: ICEM2023-112652
https://doi.org/10.1115/ICEM2023-112652
View Paper titled, MPS Method Simulation for Estimating Fuel Debris Distributions Under the Damaged Reactor Pressure Vessel of 1F Unit-2
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Topics: Accidents, Fuels, Fukushima nuclear disaster, Japan, 2011, Reactor vessels, Simulation
Journal Articles

Post-Test Analyses of the CMMR-4 Test

Takuya Yamashita, Hiroshi Madokoro, Ikken Sato
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021701.
Paper No: NERS-21-1055
https://doi.org/10.1115/1.4051443
Published Online: October 19, 2021
View Article titled, Post-Test Analyses of the CMMR-4 Test
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Topics: Blades, Boiling water reactors, Cutting, Fuels, Heating, Melting, Water, Temperature, Accidents, Permeability
Journal Articles

Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident

Yuta Abe, Takuya Yamashita, Ikken Sato, Toshio Nakagiri, Akihiro Ishimi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021113.
Paper No: NERS-19-1047
https://doi.org/10.1115/1.4045450
Published Online: January 29, 2020
View Article titled, Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident
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Topics: Fuels, Heating, Manufacturing, Plasmas (Ionized gases), Accidents, Temperature, Permeability, Melting, Blades
Proceedings Papers

Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident

Yuta Abe, Takuya Yamashita, Ikken Sato, Toshio Nakagiri, Akihiro Ishimi, Yuji Nagae
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A014, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81411
https://doi.org/10.1115/ICONE26-81411
View Paper titled, Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident
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Topics: Accidents, Fuels, Heating, Manufacturing, Melting, Plasmas (Ionized gases), Blades, Computerized tomography, Electrons, Engineering prototypes
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
Journal Articles

Strength of 316FR Joints Welded by Type 316FR/16-8-2 Filler Metals

Takuya Yamashita, Yuji Nagae, Kenichiro Satoh, Kenji Yamamoto
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Technical Briefs
J. Pressure Vessel Technol. April 2016, 138(2): 024501.
Paper No: PVT-15-1033
https://doi.org/10.1115/1.4031444
Published Online: October 6, 2015
View Article titled, Strength of 316FR Joints Welded by Type 316FR/16-8-2 Filler Metals
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Topics: Creep, Filler metals, Welded joints, Welding, Tensile strength, Ferrites (Magnetic materials), Metals, Base metals, Gas tungsten arc welding
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 a SH Wave Single Unit Electromagnetic Acoustic Transducer (EMAT) for MONJU Reactor Vessel In-Service Inspection

Yang Xu, Akihiro Tagawa, Kazunari Fujiki, Masashi Ueda, Takuya Yamashita
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 269-278, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75027
https://doi.org/10.1115/ICONE17-75027
View Paper titled, Development of a SH Wave Single Unit Electromagnetic Acoustic Transducer (EMAT) for MONJU Reactor Vessel In-Service Inspection
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Topics: Acoustics, In-service inspection, Reactor vessels, Transducers, Waves
Proceedings Papers

Development of the ISI Device for Fast Breeder Reactor MONJU Reactor Vessel

Akihiro Tagawa, Masashi Ueda, Takuya Yamashita
Proc. ASME. ICONE14, Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management, 425-432, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89230
https://doi.org/10.1115/ICONE14-89230
View Paper titled, Development of the ISI Device for Fast Breeder Reactor MONJU Reactor Vessel
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Topics: Acoustics, Breeder reactors, In-service inspection, Reactor vessels, Transducers, Inspection, Sensors, Cooling systems, Glass fibers, Irradiation (Radiation exposure)
Proceedings Papers

Finite Element Simulations of the Remote Field Eddy Current Signal in Steam Generator Tubes of Monju Fast Breeder Reactor

Ovidiu Mihalache, Yoshiyuki Imai, Masashi Ueda, Takuya Yamashita
Proc. ASME. PVP2004, Recent Advances in Nondestructive Evaluation Techniques for Material Science and Industries, 199-205, July 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: PVP2004-2837
https://doi.org/10.1115/PVP2004-2837
View Paper titled, Finite Element Simulations of the Remote Field Eddy Current Signal in Steam Generator Tubes of Monju Fast Breeder Reactor
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Topics: Boilers, Breeder reactors, Eddies (Fluid dynamics), Eddy currents (Electricity), Engineering simulation, Finite element analysis, Signals, Simulation, Computer simulation, Errors
Proceedings Papers

Characterization of SH Wave Electromagnetic Acoustic Transducer (EMAT) at Elevated Temperature

Yang Xu, Akihiro Tagawa, Masashi Ueda, Takuya Yamashita, Yusuke Ohtsuka, Kazunori Osafune, Masahiro Nishikawa
Proc. ASME. PVP2004, Recent Advances in Nondestructive Evaluation Techniques for Material Science and Industries, 177-184, July 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: PVP2004-2834
https://doi.org/10.1115/PVP2004-2834
View Paper titled, Characterization of SH Wave Electromagnetic Acoustic Transducer (EMAT) at Elevated Temperature
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Topics: Acoustics, Temperature, Transducers, Waves, Magnetic induction, Magnets, Reactor vessels, Sound pressure, Breeder reactors, Coolants