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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
Article Type: Design Innovation Paper
ASME J of Nuclear Rad Sci. April 2023, 9(2): 025001.
Paper No: NERS-21-1157
DOI: https://doi.org/10.1115/1.4054726
Published Online: June 15, 2022
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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
Paper No: ICONE28-64525
DOI: https://doi.org/10.1115/ICONE28-64525
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Topics: Artificial intelligence, Computer simulation, Innovation, Nuclear design, Nuclear reactors, Optimization, Design, Safety, Carbon, Coolants
Journal Articles

Development of In-Service Inspection Rules for Liquid-Metal Cooled Reactors Using the System Based Code Concept

Shigeru Takaya, Tai Asayama, Hiroki Yada, A. Thomas Roberts, Frank J. Schaaf, Jr.
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
J. Pressure Vessel Technol. April 2020, 142(2): 021204.
Paper No: PVT-19-1071
DOI: https://doi.org/10.1115/1.4044344
Published Online: November 27, 2019
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Topics: In-service inspection, Liquid metals, Sodium, Pipes, Heat, Breeder reactors, Fracture (Materials), Welded joints, Reliability, Engineering prototypes
Proceedings Papers

Structural Materials and Code Development for Japanese Sodium-Cooled Fast Reactors

Tai Asayama, Yugi Nagae, Takashi Wakai, Kazuyuki Tsukimori, Masaki Morishita
Proc. ASME. ETAM2014, ASME 2014 Symposium on Elevated Temperature Application of Materials for Fossil, Nuclear, and Petrochemical Industries, 296-302, March 25–27, 2014
Paper No: ETAM2014-1037
DOI: https://doi.org/10.1115/ETAM2014-1037
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Topics: Sodium fast reactors, Design, Fast neutron reactors, Japan Society of Mechanical Engineers, Construction, Cycles, Fitness-for-service, Industrial research, Leak-before-break, Reliability
Proceedings Papers

Implementation of Reliability Evaluation Into JSME Fast Reactor Codes: 1 — Current Status and Path Forward

Tai Asayama, Shigeru Takaya
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, V002T08A007, June 26–30, 2016
Paper No: ICONE24-60936
DOI: https://doi.org/10.1115/ICONE24-60936
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Topics: Fast neutron reactors, Japan Society of Mechanical Engineers, Reliability, Design, In-service inspection, Buckling, Design methodology, Engineering standards, Inspection, Stress
Proceedings Papers

Implementation of Reliability Evaluation Into JSME Fast Reactor Codes: 2 — Development of a Code Case for Seismic Buckling Evaluation Based on LRFD

Shigeru Takaya, Naoto Sasaki, Tai Asayama, Yoshio Kamishima
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, V002T08A010, June 26–30, 2016
Paper No: ICONE24-60964
DOI: https://doi.org/10.1115/ICONE24-60964
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Topics: Buckling, Fast neutron reactors, Japan Society of Mechanical Engineers, Reliability, Design, Stress, Probability, Vessels, Civil engineering, Earthquake risk
Journal Articles

Study on Minimum Wall Thickness Requirement for Seismic Buckling of Reactor Vessel Based on System Based Code Concept

Shigeru Takaya, Daigo Watanabe, Shinobu Yokoi, Yoshio Kamishima, Kenichi Kurisaka, Tai Asayama
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
J. Pressure Vessel Technol. October 2015, 137(5): 051802.
Paper No: PVT-14-1003
DOI: https://doi.org/10.1115/1.4029322
Published Online: October 1, 2015
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Topics: Buckling, Design, Earthquakes, Reliability, Stress, Wall thickness, Probability, Statistical distributions, Reactor vessels, Earthquake risk
Journal Articles

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

Yuji Nagae, Shigeru Takaya, Tai Asayama
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
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
Journal Articles

Application of the System Based Code Concept to the Determination of In-Service Inspection Requirements

Shigeru Takaya, Tai Asayama, Yoshio Kamishima, Hideo Machida, Daigo Watanabe, Satoru Nakai, Masaki Morishita
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2015, 1(1): 011004.
Paper No: NERS-14-1020
DOI: https://doi.org/10.1115/1.4026392
Published Online: February 9, 2015
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Topics: Creep, Design, Failure, Fatigue, Fracture (Materials), In-service inspection, Probability, Reliability, Safety, Stress
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

Elaboration of the System Based Code Concept — Activities in JSME and ASME: (4) Joint Efforts of JSME and ASME

Tai Asayama, Shigeru Takaya, Masaki Morishita, Frank Schaaf
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, V001T07A006, July 7–11, 2014
Paper No: ICONE22-30572
DOI: https://doi.org/10.1115/ICONE22-30572
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Topics: Japan Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Flow (Dynamics), In-service inspection, Liquid metals, Mechanical engineers, Safety, Sodium fast reactors
Proceedings Papers

Elaboration of the System Based Code Concept — Activities in JSME and ASME: (2) Development of Evaluation Tools Based on LRFD

Hideo Machida, Tai Asayama, Daigo Watanabe, Kiminobu Hojo, Masaaki Hayashi
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, V001T07A002, July 7–11, 2014
Paper No: ICONE22-30525
DOI: https://doi.org/10.1115/ICONE22-30525
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Topics: Japan Society of Mechanical Engineers, Reliability, Collapse, Design, Bending (Stress), Buckling, Cylinders, Failure, Failure mechanisms, Fatigue
Proceedings Papers

Elaboration of the System Based Code Concept — Activities in JSME and ASME: (1) Overview

Tai Asayama, Takayuki Miyagawa, Koji Dozaki, Yoshio Kamishima, Masaaki Hayashi, Hideo Machida
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, V001T07A004, July 7–11, 2014
Paper No: ICONE22-30567
DOI: https://doi.org/10.1115/ICONE22-30567
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Topics: Japan Society of Mechanical Engineers, Reliability, ASME Boiler and Pressure Vessel Code, Collaboration, Design, Engineering standards, In-service inspection, Liquid metals, Mechanical engineers, Sodium fast reactors
Journal Articles

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

Shigeru Takaya, Yuji Nagae, Tai Asayama
Journal: Journal of Pressure Vessel Technology
Article Type: Research-Article
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 Limit State Design for Fast Reactor by System Based Code

Daigo Watanabe, Yasuharu Chuman, Tai Asayama, Shigeru Takaya, Hideo Machida, Yoshio Kamishima
Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A031, July 14–18, 2013
Paper No: PVP2013-97154
DOI: https://doi.org/10.1115/PVP2013-97154
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Topics: Design, Fast neutron reactors, Stress, Acceptance criteria, Design methodology, Plant design, Reactor vessels
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: (1) Overview

Tai Asayama, Koji Dozaki, Tomomi Otani, Takanari Inatomi, Masanori Ando
Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A046, July 14–18, 2013
Paper No: PVP2013-98061
DOI: https://doi.org/10.1115/PVP2013-98061
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Topics: Construction, Design, Fast neutron reactors, JSME Standards, Japan Society of Mechanical Engineers, Breeder reactors, Carbon, Creep, Engineering prototypes, Evaluation methods
Proceedings Papers

Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (6) Design Margin Assessment for the New Materials to the Rules

Masanori Ando, Sota Watanabe, Koichi Kikuchi, Tomomi Otani, Kenichiro Satoh, Kazuyuki Tsukimori, Tai Asayama
Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A040, July 14–18, 2013
Paper No: PVP2013-97803
DOI: https://doi.org/10.1115/PVP2013-97803
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Topics: Construction, Design, Fast neutron reactors, JSME Standards, Japan Society of Mechanical Engineers, Creep, Damage, Fatigue, Finite element analysis, Materials properties
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)