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Proceedings Papers

Multiple Knowledge Exploration Functions for Advanced Reactor Design and Safety in Knowledge Management System Implemented in the ARKADIA

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Akiyuki Seki, Yuki Kondo, Ryuta Hashidate, Masanori Yoshikawa, Kenji Yokoyama, Shigeru Takaya, Yasuhiro Enuma, Taira Hazama, Takashi Wakai, Tai Asayama
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A012, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131784
https://doi.org/10.1115/ICONE31-131784
View Paper titled, Multiple Knowledge Exploration Functions for Advanced Reactor Design and Safety in Knowledge Management System Implemented in the ARKADIA
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Topics: Design, Knowledge management, Safety, Computer-aided design, Information retrieval, Sodium fast reactors, Artificial intelligence, Carbon, Computer simulation, Engineering drawings
Proceedings Papers

Time Series Analysis With Combined Learning Approach for Anomaly Detection in Nuclear Power Plants

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Feiyan Dong, Shi Chen, Kazuyuki Demachi, Masanori Yoshikawa, Akiyuki Seki, Shigeru Takaya
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A032, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134602
https://doi.org/10.1115/ICONE31-134602
View Paper titled, Time Series Analysis With Combined Learning Approach for Anomaly Detection in Nuclear Power Plants
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Topics: Nuclear power stations, Safety, Time series
Proceedings Papers

Stress Intensity Factor Solutions for Circumferential Through-Wall Cracks Applicable to Pool Type Sodium Cooled Fast Reactors

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Hiroki Yada, Shigeru Takaya, Hideo Machida
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A010, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134552
https://doi.org/10.1115/ICONE31-134552
View Paper titled, Stress Intensity Factor Solutions for Circumferential Through-Wall Cracks Applicable to Pool Type Sodium Cooled Fast Reactors
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Topics: Cylinders, Fast neutron reactors, Finite element analysis, Fracture (Materials), Sodium, Stress
Proceedings Papers

Comparison Between Fracture Mechanics Evaluation Methods in ASME Boiler & Pressure Vessel Code, Section XI and Those in JSME Leak-Before-Break Evaluation Guidelines for Sodium-Cooled Fast Reactors

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Hiroki Yada, Shigeru Takaya, Hideo Machida
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A003, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-106562
https://doi.org/10.1115/PVP2023-106562
View Paper titled, Comparison Between Fracture Mechanics Evaluation Methods in ASME Boiler & Pressure Vessel Code, Section XI and Those in JSME Leak-Before-Break Evaluation Guidelines for Sodium-Cooled Fast Reactors
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Topics: Boilers, Evaluation methods, Fracture (Materials), Fracture (Process), Fracture mechanics, Japan Society of Mechanical Engineers, Leak-before-break, Pressure vessels, Sodium fast reactors
Proceedings Papers

A Weakly Supervised Time Series Analysis Framework for Anomaly Detection in Nuclear Power Plants

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Feiyan Dong, Shi Chen, Kazuyuki Demachi, Masanori Yoshikawa, Akiyuki Seki, Shigeru Takaya
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A050, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91609
https://doi.org/10.1115/ICONE29-91609
View Paper titled, A Weakly Supervised Time Series Analysis Framework for Anomaly Detection in Nuclear Power Plants
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Topics: Condition monitoring, Nuclear power stations, Time series
Proceedings Papers

Proposal of Detailed Procedures of Determining Rational In-Service Inspection Requirements Based on System Based Code Concept

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Hiroki Yada, Shigeru Takaya, Kyoichi Morohoshi, Shinobu Yokoi
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A013, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90542
https://doi.org/10.1115/ICONE29-90542
View Paper titled, Proposal of Detailed Procedures of Determining Rational In-Service Inspection Requirements Based on System Based Code Concept
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Topics: In-service inspection, Inspection, Sodium fast reactors
Journal Articles

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

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Shigeru Takaya, Tai Asayama, Hiroki Yada, A. Thomas Roberts, Frank J. Schaaf, Jr.
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. April 2020, 142(2): 021204.
Paper No: PVT-19-1071
https://doi.org/10.1115/1.4044344
Published Online: November 27, 2019
View Articletitled, Development of In-Service Inspection Rules for Liquid-Metal Cooled Reactors Using the System Based Code Concept
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Topics: In-service inspection, Liquid metals, Sodium, Pipes, Heat, Breeder reactors, Fracture (Materials), Welded joints, Reliability, Engineering prototypes
Proceedings Papers

Proposal of a Simple Evaluation Method for Sloshing Impact Pressure on Flat Roofs

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Shigeru Takaya, Tatsuya Fujisaki
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A031, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82562
https://doi.org/10.1115/ICONE26-82562
View Paper titled, Proposal of a Simple Evaluation Method for Sloshing Impact Pressure on Flat Roofs
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Topics: Evaluation methods, Pressure, Roofs, Sloshing, Computational fluid dynamics, Damage, Earthquakes, Fast neutron reactors, Reactor vessels, Slabs
Proceedings Papers

Evaluation Method of Response Reliability During an Accident and its Applicability to Fast Reactor Plants

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Masaaki Suzuki, Kazuyuki Demachi, Shigeru Takaya, Yoshitaka Chikazawa
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A046, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82567
https://doi.org/10.1115/ICONE26-82567
View Paper titled, Evaluation Method of Response Reliability During an Accident and its Applicability to Fast Reactor Plants
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Topics: Accidents, Evaluation methods, Fast neutron reactors, Reliability, Safety, Nuclear power stations
Proceedings Papers

Numerical Analysis of Flow-Induced Vibration of Large Diameter Pipe With Short Elbow

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Shigeru Takaya, Tatsuya Fujisaki, Masaaki Tanaka
Proc. ASME. PVP2017, Volume 4: Fluid-Structure Interaction, V004T04A006, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65601
https://doi.org/10.1115/PVP2017-65601
View Paper titled, Numerical Analysis of Flow-Induced Vibration of Large Diameter Pipe With Short Elbow
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Topics: Flow-induced vibrations, Numerical analysis, Pipes, Pressure, Design, Stress, Computer simulation, Flow (Dynamics), Construction, Cooling systems
Proceedings Papers

Numerical Analysis of Unsteady Phenomena in Upper Plenum and Hot-Leg Piping System of Advanced Loop-Type Sodium Cooled Fast Reactor

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Shigeru Takaya, Tatsuya Fujisaki, Masaaki Tanaka
Proc. ASME. PVP2016, Volume 3: Design and Analysis, V003T03A003, July 17–21, 2016
Publisher: American Society of Mechanical Engineers
Paper No: PVP2016-63845
https://doi.org/10.1115/PVP2016-63845
View Paper titled, Numerical Analysis of Unsteady Phenomena in Upper Plenum and Hot-Leg Piping System of Advanced Loop-Type Sodium Cooled Fast Reactor
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Topics: Numerical analysis, Piping systems, Sodium fast reactors, Flow (Dynamics), Pipes, Design, Simulation results, Swirling flow, Computer simulation, Construction
Proceedings Papers

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60936
https://doi.org/10.1115/ICONE24-60936
View Paper titled, Implementation of Reliability Evaluation Into JSME Fast Reactor Codes: 1 — Current Status and Path Forward
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60964
https://doi.org/10.1115/ICONE24-60964
View Paper titled, Implementation of Reliability Evaluation Into JSME Fast Reactor Codes: 2 — Development of a Code Case for Seismic Buckling Evaluation Based on LRFD
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Topics: Buckling, Fast neutron reactors, Japan Society of Mechanical Engineers, Reliability, Design, Stress, Probability, Vessels, Civil engineering, Earthquake risk
Proceedings Papers

Development of Integrated Numerical Analysis Model for Unsteady Phenomena in Upper Plenum and Hot-Leg Piping System of Japan Sodium-Cooled Fast Reactor

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Shigeru Takaya, Masaaki Tanaka, Tatsuya Fujisaki
Proc. ASME. PVP2015, Volume 3: Design and Analysis, V003T03A001, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45248
https://doi.org/10.1115/PVP2015-45248
View Paper titled, Development of Integrated Numerical Analysis Model for Unsteady Phenomena in Upper Plenum and Hot-Leg Piping System of Japan Sodium-Cooled Fast Reactor
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Topics: Numerical analysis, Piping systems, Sodium fast reactors, Flow (Dynamics), Stress, Vibration analysis, Computational fluid dynamics, Design, Engineering prototypes, Flow-induced vibrations
Journal Articles

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

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Shigeru Takaya, Daigo Watanabe, Shinobu Yokoi, Yoshio Kamishima, Kenichi Kurisaka, Tai Asayama
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. October 2015, 137(5): 051802.
Paper No: PVT-14-1003
https://doi.org/10.1115/1.4029322
Published Online: October 1, 2015
View Articletitled, Study on Minimum Wall Thickness Requirement for Seismic Buckling of Reactor Vessel Based on System Based Code Concept
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Topics: Buckling, Design, Earthquakes, Reliability, Stress, Wall thickness, Probability, Statistical distributions, Reactor vessels, Earthquake risk
Journal Articles

Evaluation of Fatigue Strength of Similar and Dissimilar Welded Joints of Modified 9Cr–1Mo Steel

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Shigeru Takaya
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. February 2016, 138(1): 011402.
Paper No: PVT-15-1003
https://doi.org/10.1115/1.4030932
Published Online: August 26, 2015
View Articletitled, Evaluation of Fatigue Strength of Similar and Dissimilar Welded Joints of Modified 9Cr–1Mo Steel
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Topics: Fatigue life, Steel, Welded joints, Metals, Fatigue, Base metals
Journal Articles

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

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Yuji Nagae, Shigeru Takaya, Tai Asayama
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Research-Article
J. Pressure Vessel Technol. August 2015, 137(4): 041407.
Paper No: PVT-14-1096
https://doi.org/10.1115/1.4028497
Published Online: August 1, 2015
View Articletitled, Development of Creep–Fatigue Evaluation Method for 316FR Stainless Steel
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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

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

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

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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

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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