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Proceedings Papers

Features of a BWR Neutron Absorber Melt Relocation in an Oxidative Environment During the CLADS-MADE-02 Test

Anton Pshenichnikov, Yuji Nagae, Masaki Kurata

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T11A012, August 4–6, 2021

Paper No: ICONE28-65129

DOI: https://doi.org/10.1115/ICONE28-65129

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Topics: Accidents, Blades, Boiling water reactors, Fukushima nuclear disaster, Japan, 2011, Neutrons

Proceedings Papers

Development of Three-Dimensional Distribution Visualization Technology for Boron Using Energy Resolved Neutron-Imaging System (RADEN)

Yuta Abe, Yusuke Tsuchikawa, Tetsuya Kai, Yoshihiro Matsumoto, Joseph D. Parker, Takenao Shinohara, Yuji Ohishi, Takashi Kamiyama, Yuji Nagae, Ikken Sato

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A050, August 4–5, 2020

Paper No: ICONE2020-16723

DOI: https://doi.org/10.1115/ICONE2020-16723

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Topics: Boron, Fukushima nuclear disaster, Japan, 2011, Imaging, Melting, Neutrons, Nuclear decommissioning, Nuclear power stations, Visualization

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

Paper No: ICONE26-81411

DOI: https://doi.org/10.1115/ICONE26-81411

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Topics: Accidents, Fuels, Heating, Manufacturing, Melting, Plasmas (Ionized gases), Blades, Computerized tomography, Electrons, Engineering prototypes

Journal Articles

Application of Nontransfer Type Plasma Heating Technology for Core-Material-Relocation Tests in Boiling Water Reactor Severe Accident Conditions

Yuta Abe, Ikken Sato, Toshio Nakagiri, Akihiro Ishimi, Yuji Nagae

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020901.

Paper No: NERS-16-1117

DOI: https://doi.org/10.1115/1.4038911

Published Online: March 5, 2018

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Topics: Heating, Plasmas (Ionized gases), Boiling water reactors, Accidents

Proceedings Papers

Preparation for a New Experimental Program Addressing Core-Material-Relocation Behavior During Severe Accident With BWR Design Conditions: Conduction of Preparatory Tests Applying Non-Transfer-Type Plasma Heating Technology

Yuta Abe, Ikken Sato, Akihiro Ishimi, Toshio Nakagiri, Yuji Nagae

Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T07A004, June 26–30, 2016

Paper No: ICONE24-60249

DOI: https://doi.org/10.1115/ICONE24-60249

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Topics: Accidents, Boiling water reactors, Design, Heat conduction, Heating, Plasmas (Ionized gases), Blades, Rods, Uncertainty

Proceedings Papers

Evaluation Method of Creep-Fatigue Life for 316FR Weldment

Yuji Nagae, Kenji Yamamoto, Tomomi Otani

Proc. ASME. PVP2015, Volume 6A: Materials and Fabrication, V06AT06A051, July 19–23, 2015

Paper No: PVP2015-45513

DOI: https://doi.org/10.1115/PVP2015-45513

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Topics: Creep, Evaluation methods, Fatigue, Fillers (Materials), Stainless steel, Base metals, Mechanical properties, Failure mechanisms, Fast neutron reactors, Filler metals

Journal Articles

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

Takuya Yamashita, Yuji Nagae, Kenichiro Satoh, Kenji Yamamoto

J. Pressure Vessel Technol. April 2016, 138(2): 024501.

Paper No: PVT-15-1033

DOI: https://doi.org/10.1115/1.4031444

Published Online: October 6, 2015

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Topics: Creep, Filler metals, Welded joints, Welding, Tensile strength, Ferrites (Magnetic materials), Metals, Base metals, Gas tungsten arc welding

Journal Articles

Development of Creep–Fatigue Evaluation Method for 316FR Stainless Steel

Yuji Nagae, Shigeru Takaya, Tai Asayama

J. Pressure Vessel Technol. August 2015, 137(4): 041407.

Paper No: PVT-14-1096

DOI: https://doi.org/10.1115/1.4028497

Published Online: August 1, 2015

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Topics: Creep, Fatigue, Fatigue life, Stainless steel, Damage

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

Paper No: PVP2014-28853

DOI: https://doi.org/10.1115/PVP2014-28853

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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

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

Paper No: PVP2014-28689

DOI: https://doi.org/10.1115/PVP2014-28689

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Topics: Design, Sodium fast reactors, Strength (Materials), Steel, Stress, Temperature, Boilers, Forgings (Products), Fracture (Materials), Fracture (Process)

Journal Articles

Development of Creep-Fatigue Evaluation Method for Modified 9Cr-1Mo Steel

Shigeru Takaya, Yuji Nagae, Tai Asayama

J. Pressure Vessel Technol. June 2014, 136(3): 031404.

Paper No: PVT-13-1199

DOI: https://doi.org/10.1115/1.4026497

Published Online: February 27, 2014

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Topics: Creep, Fatigue, Relaxation (Physics), Stress, Steel, Failure, Ductility, Evaluation methods

Proceedings Papers

Extrapolation of Creep Strength by Fracture Energy for 316FR Stainless Steel at 823K

Yuji Nagae, Tai Asayama

Proc. ASME. PVP2013, Volume 6A: Materials and Fabrication, V06AT06A036, July 14–18, 2013

Paper No: PVP2013-97807

DOI: https://doi.org/10.1115/PVP2013-97807

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Topics: Creep, Fracture (Materials), Fracture (Process), Stainless steel, Rupture, Density, Design, Elongation, Failure, Fast neutron reactors

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

Paper No: PVP2013-97608

DOI: https://doi.org/10.1115/PVP2013-97608

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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: (4) Creep–Fatigue Evaluation Method for Modified 9Cr–1Mo Steel

Shigeru Takaya, Yuji Nagae, Tai Asayama

Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A035, July 14–18, 2013

Paper No: PVP2013-97609

DOI: https://doi.org/10.1115/PVP2013-97609

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Topics: Construction, Creep, Design, Evaluation methods, Fast neutron reactors, Fatigue, JSME Standards, Steel, Failure, Relaxation (Physics)

Proceedings Papers

Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (5) Creep-Fatigue Evaluation Method for 316FR Stainless Steel

Yuji Nagae, Shigeru Takaya, Tai Asayama

Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A041, July 14–18, 2013

Paper No: PVP2013-97806

DOI: https://doi.org/10.1115/PVP2013-97806

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Topics: Construction, Creep, Design, Evaluation methods, Fast neutron reactors, Fatigue, JSME Standards, Stainless steel, Failure, Rupture

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

Paper No: PVP2013-97611

DOI: https://doi.org/10.1115/PVP2013-97611

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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

Paper No: PVP2010-26014

DOI: https://doi.org/10.1115/PVP2010-26014

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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

Paper No: PVP2009-77984

DOI: https://doi.org/10.1115/PVP2009-77984

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Topics: Breeder reactors, Strength (Materials), Design, Steel, Boilers, Engineering standards, Japan Society of Mechanical Engineers, ASTM International, Circuits, Construction

Proceedings Papers

Nondestructive Evaluation of Neutron Irradiation Damage on Austenitic Stainless Steels by Measurement of Magnetic Flux Density

Shigeru Takaya, Yuji Nagae, Kazumi Aoto, Ichiro Yamagata, Shoichi Ichikawa, Shotaro Konno, Ryuichiro Ogawa, Eiichi Wakai

Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 371-374, July 12–16, 2009

Paper No: ICONE17-75215

DOI: https://doi.org/10.1115/ICONE17-75215

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Topics: Damage, Irradiation (Radiation exposure), Magnetic induction, Neutrons, Nondestructive evaluation, Stainless steel, Sensors, Atoms, Breeder reactors, Displacement

Journal citation

NARROW

Features of a BWR Neutron Absorber Melt Relocation in an Oxidative Environment During the CLADS-MADE-02 Test

Development of Three-Dimensional Distribution Visualization Technology for Boron Using Energy Resolved Neutron-Imaging System (RADEN)

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

Application of Nontransfer Type Plasma Heating Technology for Core-Material-Relocation Tests in Boiling Water Reactor Severe Accident Conditions

Preparation for a New Experimental Program Addressing Core-Material-Relocation Behavior During Severe Accident With BWR Design Conditions: Conduction of Preparatory Tests Applying Non-Transfer-Type Plasma Heating Technology

Evaluation Method of Creep-Fatigue Life for 316FR Weldment

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

Development of Creep–Fatigue Evaluation Method for 316FR Stainless Steel

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

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

Development of Creep-Fatigue Evaluation Method for Modified 9Cr-1Mo Steel

Extrapolation of Creep Strength by Fracture Energy for 316FR Stainless Steel at 823K

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

Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (4) Creep–Fatigue Evaluation Method for Modified 9Cr–1Mo Steel

Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (5) Creep-Fatigue Evaluation Method for 316FR Stainless Steel

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

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

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

Nondestructive Evaluation of Neutron Irradiation Damage on Austenitic Stainless Steels by Measurement of Magnetic Flux Density

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