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Journal Articles

ARKADIA—For the Innovation of Advanced Nuclear Reactor Design

Hiroyuki Ohshima, Tai Asayama, Tomohiro Furukawa, Masaaki Tanaka, Akihiro Uchibori, Takashi Takata, Akiyuki Seki, Yasuhiro Enuma
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Design Innovation Paper
ASME J of Nuclear Rad Sci. April 2023, 9(2): 025001.
Paper No: NERS-21-1157
https://doi.org/10.1115/1.4054726
Published Online: June 15, 2022
View Article titled, ARKADIA—For the Innovation of Advanced Nuclear Reactor Design
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Topics: Design, Optimization, Safety, Thermal hydraulics, Nuclear design, Nuclear reactors, Computer simulation
Proceedings Papers

ARKADIA – for the Innovation of Advanced Nuclear Reactor Design

Hiroyuki Ohshima, Tai Asayama, Tomohiro Furukawa, Masaaki Tanaka, Takashi Takata, Yasuhiro Enuma
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T03A007, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64525
https://doi.org/10.1115/ICONE28-64525
View Paper titled, ARKADIA – for the Innovation of Advanced Nuclear Reactor Design
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Topics: Artificial intelligence, Computer simulation, Innovation, Nuclear design, Nuclear reactors, Optimization, Design, Safety, Carbon, Coolants
Proceedings Papers

Development of the Pump-Integrated Intermediate Heat Exchanger in Advanced Loop-Type Sodium-Cooled Fast Reactor for Demonstration

Katsunori Amano, Yasuhiro Enuma, Satoshi Futagami, Tomoyuki Inoue, Sota Watanabe
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, V002T06A004, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60064
https://doi.org/10.1115/ICONE24-60064
View Paper titled, Development of the Pump-Integrated Intermediate Heat Exchanger in Advanced Loop-Type Sodium-Cooled Fast Reactor for Demonstration
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Topics: Heat exchangers, Pumps, Sodium fast reactors, Design, Safety, Coolants, Earthquakes, Leakage, Maintainability, Nuclear power
Proceedings Papers

A Study on the Straight Double-Walled Tube Steam Generator Design Against Sodium-Water Reaction in DECs

Hironori Kanda, Yasuhiro Enuma, Satoshi Futagami, Masaya Kawamura, Hiroshi Ushiki, Shinya Ogumo, Takashi Ichihara, Takashi Nakashima
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, V002T06A009, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60156
https://doi.org/10.1115/ICONE24-60156
View Paper titled, A Study on the Straight Double-Walled Tube Steam Generator Design Against Sodium-Water Reaction in DECs
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Topics: Boilers, Design, Sodium, Water, Failure, Sodium fast reactors, Water leakage, Contact resistance, Temperature, Leakage
Journal Articles

Comparison and Assessment of the Creep-Fatigue Evaluation Methods With Notched Specimen Made of Mod.9Cr-1Mo Steel

Masanori Ando, Yuichi Hirose, Takanori Karato, Sota Watanabe, Osamu Inoue, Nobuchika Kawasaki, Yasuhiro Enuma
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. August 2014, 136(4): 041406.
Paper No: PVT-12-1178
https://doi.org/10.1115/1.4026852
Published Online: April 16, 2014
View Article titled, Comparison and Assessment of the Creep-Fatigue Evaluation Methods With Notched Specimen Made of Mod.9Cr-1Mo Steel
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Topics: Creep, Fatigue, Stress
Journal Articles

Development of Leak-Before-Break Assessment Method for Japan Sodium Cooled Fast Reactor Pipe—Part 1 Crack Opening Displacement Assessment of Thin Wall Pipes Made of Modified 9Cr-1Mo Steel

Takashi Wakai, Hideo Machida, Manabu Arakawa, Shinji Yoshida, Yasuhiro Enuma
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. February 2013, 135(1): 011401.
Paper No: PVT-11-1116
https://doi.org/10.1115/1.4007642
Published Online: December 4, 2012
View Article titled, Development of Leak-Before-Break Assessment Method for Japan Sodium Cooled Fast Reactor Pipe—Part 1 Crack Opening Displacement Assessment of Thin Wall Pipes Made of Modified 9Cr-1Mo Steel
Open the PDF for Development of Leak-Before-Break Assessment Method for Japan Sodium Cooled Fast Reactor Pipe—Part 1 Crack Opening Displacement Assessment of Thin Wall Pipes Made of Modified 9Cr-1Mo Steel in another window
Topics: Displacement, Finite element analysis, Fracture (Materials), Pipes, Sodium fast reactors, Steel, Tension, Thin wall structures, Stress, Leak-before-break
Journal Articles

Verification of the Estimation Methods of Strain Range in Notched Specimens Made of Mod.9Cr-1Mo Steel

Masanori Ando, Yuichi Hirose, Shingo Date, Sota Watanabe, Yasuhiro Enuma, Nobuchika Kawasaki
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. December 2012, 134(6): 061403.
https://doi.org/10.1115/1.4006902
Published Online: October 18, 2012
View Article titled, Verification of the Estimation Methods of Strain Range in Notched Specimens Made of Mod.9Cr-1Mo Steel
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Topics: Cycles, Fatigue, Fatigue testing, Finite element analysis, Japan Society of Mechanical Engineers, Stress, Failure, Fracture (Materials), Steel, Design
Proceedings Papers

An Evaluation Method for Plastic Buckling of Cantilever Type Pipes Controlled by Displacement Loads: Part 1—Proposal of the Estimation Method and the Criterion

Masanori Ando, Taiji Tezuka, Toshio Nakamura, Tomohiro Okawa, Yasuhiro Enuma, Nobuchika Kawasaki, Kazuyuki Tsukimori
Proc. ASME. PVP2011, Volume 3: Design and Analysis, 233-241, July 17–21, 2011
Publisher: American Society of Mechanical Engineers
Paper No: PVP2011-57544
https://doi.org/10.1115/PVP2011-57544
View Paper titled, An Evaluation Method for Plastic Buckling of Cantilever Type Pipes Controlled by Displacement Loads: Part 1—Proposal of the Estimation Method and the Criterion
Open the PDF for An Evaluation Method for Plastic Buckling of Cantilever Type Pipes Controlled by Displacement Loads: Part 1—Proposal of the Estimation Method and the Criterion in another window
Topics: Buckling, Cantilevers, Displacement, Evaluation methods, Pipes, Stress, Finite element analysis, Materials properties, Steel, Work hardening
Proceedings Papers

An Evaluation Method for Plastic Buckling of Cantilever Type Pipes Controlled by Displacement Loads: Part 2—Verification of Proposal Method by Buckling Test

Masanori Ando, Taiji Tezuka, Toshio Nakamura, Tomohiro Okawa, Yasuhiro Enuma, Nobuchika Kawasaki, Kazuyuki Tsukimori
Proc. ASME. PVP2011, Volume 3: Design and Analysis, 243-250, July 17–21, 2011
Publisher: American Society of Mechanical Engineers
Paper No: PVP2011-57548
https://doi.org/10.1115/PVP2011-57548
View Paper titled, An Evaluation Method for Plastic Buckling of Cantilever Type Pipes Controlled by Displacement Loads: Part 2—Verification of Proposal Method by Buckling Test
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Topics: Buckling, Cantilevers, Displacement, Evaluation methods, Pipes, Stress, Finite element analysis, Breeder reactors, Deformation, Design
Proceedings Papers

Comparison of Creep-Fatigue Evaluation Methods With Notched Specimens Made of Mod.9Cr-1Mo Steel

Masanori Ando, Yuichi Hirose, Takanori Karato, Sota Watanabe, Osamu Inoue, Nobuchika Kawasaki, Yasuhiro Enuma
Proc. ASME. PVP2011, Volume 6: Materials and Fabrication, Parts A and B, 177-187, July 17–21, 2011
Publisher: American Society of Mechanical Engineers
Paper No: PVP2011-57532
https://doi.org/10.1115/PVP2011-57532
View Paper titled, Comparison of Creep-Fatigue Evaluation Methods With Notched Specimens Made of Mod.9Cr-1Mo Steel
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Topics: Creep, Evaluation methods, Fatigue, Steel, Finite element analysis, Japan Society of Mechanical Engineers, Stress, Cycles, Design, Electromagnetic induction
Proceedings Papers

Development of LBB Assessment Method for Japanese Sodium Cooled Fast Reactor (JSFR) Pipes: 1—Study on the Premise for the Standardization of Assessment Procedure

Takashi Wakai, Hideo Machida, Yasuhiro Enuma, Tai Asayama
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B, 709-714, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25243
https://doi.org/10.1115/PVP2010-25243
View Paper titled, Development of LBB Assessment Method for Japanese Sodium Cooled Fast Reactor (JSFR) Pipes: 1—Study on the Premise for the Standardization of Assessment Procedure
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Topics: Pipes, Sodium fast reactors, Steel, Fracture (Materials), Leakage, Japan Society of Mechanical Engineers, Stress, Construction, Creep, Design
Proceedings Papers

Development of LBB Assessment Method for Japanese Sodium Cooled Fast Reactor (JSFR) Pipes: 3—Fracture Assessment Methods Considering Compliance at a Crack Part

Takashi Wakai, Hideo Machida, Shinji Yoshida, Yasuhiro Enuma, Tai Asayama
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B, 715-724, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25244
https://doi.org/10.1115/PVP2010-25244
View Paper titled, Development of LBB Assessment Method for Japanese Sodium Cooled Fast Reactor (JSFR) Pipes: 3—Fracture Assessment Methods Considering Compliance at a Crack Part
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Topics: Fracture (Materials), Pipes, Sodium fast reactors, Piping systems, Stiffness, Stress, Design, Leak-before-break, Pressure, Sodium
Proceedings Papers

Development of LBB Assessment Method for Japanese Sodium Cooled Fast Reactor (JSFR) Pipes: 2—Crack Opening Displacement Assessment of Thin Wall Pipes Made of Modified 9Cr-1Mo Steel

Takashi Wakai, Hideo Machida, Manabu Arakawa, Yasuhiro Enuma, Tai Asayama
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B, 725-731, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25249
https://doi.org/10.1115/PVP2010-25249
View Paper titled, Development of LBB Assessment Method for Japanese Sodium Cooled Fast Reactor (JSFR) Pipes: 2—Crack Opening Displacement Assessment of Thin Wall Pipes Made of Modified 9Cr-1Mo Steel
Open the PDF for Development of LBB Assessment Method for Japanese Sodium Cooled Fast Reactor (JSFR) Pipes: 2—Crack Opening Displacement Assessment of Thin Wall Pipes Made of Modified 9Cr-1Mo Steel in another window
Topics: Displacement, Fracture (Materials), Pipes, Sodium fast reactors, Steel, Thin wall structures, Evaluation methods, Finite element analysis, Leakage, Sodium
Proceedings Papers

Verification of the Prediction Methods of Strain Range in Notched Specimens Made of Mod.9Cr-1Mo

Masanori Ando, Yuichi Hirose, Shingo Date, Sota Watanabe, Yasuhiro Enuma, Nobuchika Kawasaki
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 1, 323-334, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25489
https://doi.org/10.1115/PVP2010-25489
View Paper titled, Verification of the Prediction Methods of Strain Range in Notched Specimens Made of Mod.9Cr-1Mo
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Topics: Creep, Damage, Deformation, Design, Electromagnetic induction, Fatigue, Fatigue life, Fatigue testing, Finite element analysis, Fracture (Materials)
Proceedings Papers

HLMC Fast Reactor With Complete Natural Circulation

Yasuhiro Enuma, Tomoyasu Mizuno, Takatsugu Mihara, Mamoru Konomura, Makoto Mito, Mikio Tanji
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 599-605, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22223
https://doi.org/10.1115/ICONE10-22223
View Paper titled, HLMC Fast Reactor With Complete Natural Circulation
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Topics: Fast neutron reactors, Conceptual design, Construction, Coolants, Cycles, Liquid metals, Public utilities, Safety