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Proceedings Papers

Study on Promoting Use of Repair, Replacement and Mitigation Techniques in Maintenance Activities of Nuclear Power Plants

Koji Dozaki, Takayuki Aoki, Koji Koyama, Masanori Kanno, Ryoichi Saeki
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A062, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84512
https://doi.org/10.1115/PVP2018-84512
View Paper titled, Study on Promoting Use of Repair, Replacement and Mitigation Techniques in Maintenance Activities of Nuclear Power Plants
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Topics: Maintenance, Nuclear power stations, Inspection, Hardware, Countermeasures, Nuclear power, Plant construction, Public utilities, Regulations, Risk
Proceedings Papers

Rules for Temporary Repair Techniques in JSME Fitness-for-Service Code and Their Challenges

Koji Dozaki, Hiroyuki Kobayashi, Hiroyuki Adachi, Katsuhide Muraoka, Yusuke Kono
Proc. ASME. PVP2015, Volume 1B: Codes and Standards, V01BT01A060, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45903
https://doi.org/10.1115/PVP2015-45903
View Paper titled, Rules for Temporary Repair Techniques in JSME Fitness-for-Service Code and Their Challenges
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Topics: Fitness-for-service, Japan Society of Mechanical Engineers, Maintenance, Design, Leakage, Nuclear power stations, Adhesion, Energy engineering, Flanges, Inspection
Proceedings Papers

Studies on Maintainability and Repairability for Japan Sodium-Cooled Fast Reactor (JSFR)

Kenichi Isono, Shigenobu Kubo, Yoshitaka Chikazawa, Koji Dozaki, Takeaki Oya, Masahiro Yui
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A007, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30175
https://doi.org/10.1115/ICONE22-30175
View Paper titled, Studies on Maintainability and Repairability for Japan Sodium-Cooled Fast Reactor (JSFR)
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Topics: Coolants, Design, Light water reactors, Maintainability, Maintenance, Plant design, Power stations, Sodium fast reactors
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30567
https://doi.org/10.1115/ICONE22-30567
View Paper titled, Elaboration of the System Based Code Concept — Activities in JSME and ASME: (1) Overview
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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
Proceedings Papers

Crack Growth Behavior and Preventive Maintenance for Reactor Internals With Cracks in Tokai-2 Nuclear Power Plant

Takushi Fujino, Takeshi Terakado, Koji Dozaki, Nobuo Ito, Kunihiro Hasegawa
Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A050, July 14–18, 2013
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-97257
https://doi.org/10.1115/PVP2013-97257
View Paper titled, Crack Growth Behavior and Preventive Maintenance for Reactor Internals With Cracks in Tokai-2 Nuclear Power Plant
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Topics: Fracture (Materials), Maintenance, Nuclear power stations, Inspection, Japan Society of Mechanical Engineers, Shapes, Crack propagation, Cycles, Metals, Shot peening
Proceedings Papers

Development of Fatigue Assessment Method Based on Flaw Tolerance Concept

Seiji Asada, Takeda Shuhei, Taiji Hirasawa, Toshiyuki Saito, Itaru Saito, Koji Dozaki
Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A039, July 14–18, 2013
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-97773
https://doi.org/10.1115/PVP2013-97773
View Paper titled, Development of Fatigue Assessment Method Based on Flaw Tolerance Concept
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Topics: Fatigue, Evaluation methods, Japan Society of Mechanical Engineers, Energy generation, JSME Standards, Nondestructive evaluation, Nuclear power
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-98061
https://doi.org/10.1115/PVP2013-98061
View Paper titled, Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (1) Overview
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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

Strain Rate Evaluation of Some Typical Nuclear Power Plant Components During Plant Operation

Koji Dozaki, Hiromasa Chitose, Hiroshi Ogawa, Hideo Machida
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 7, 95-101, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-26086
https://doi.org/10.1115/PVP2010-26086
View Paper titled, Strain Rate Evaluation of Some Typical Nuclear Power Plant Components During Plant Operation
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Topics: Boiling water reactors, Design, Dynamic testing (Materials), Evaluation methods, Failure, Failure mechanisms, Fatigue, Fatigue life, Finite element methods, Nuclear power stations
Proceedings Papers

Current Status of RRA Rules Development in JSME Fitness-for-Service Code

Koji Dozaki, Satoshi Yamamoto, Koji Koyama
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 1, 1023-1029, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-26117
https://doi.org/10.1115/PVP2010-26117
View Paper titled, Current Status of RRA Rules Development in JSME Fitness-for-Service Code
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Topics: Fitness-for-service, Japan Society of Mechanical Engineers, Engineering standards, Inspection, Maintenance, Safety, In-service inspection, Mechanical engineers, Nuclear power
Journal Articles

Industry Practice for the Neutron Irradiation Embrittlement of Reactor Pressure Vessels in Japan

Norimichi Yamashita, Masanobu Iwasaki, Koji Dozaki, Naoki Soneda
Journal: Journal of Engineering for Gas Turbines and Power
Publisher: ASME
Article Type: Research Papers
J. Eng. Gas Turbines Power. October 2010, 132(10): 102919.
https://doi.org/10.1115/1.4001057
Published Online: July 9, 2010
View Article titled, Industry Practice for the Neutron Irradiation Embrittlement of Reactor Pressure Vessels in Japan
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Topics: Embrittlement, Irradiation (Radiation exposure), Neutrons, Surveillance, Steel, Reactor vessels
Proceedings Papers

Study on Requirements to be Fulfilled With Rules for Repair Replacement Activities in JSME Code on Fitness-for-Service

Akira Nishikawa, Koji Dozaki, Koji Koyama, Kazuyuki Asada
Proc. ASME. PVP2009, Volume 1: Codes and Standards, 615-619, July 26–30, 2009
Publisher: American Society of Mechanical Engineers
Paper No: PVP2009-77112
https://doi.org/10.1115/PVP2009-77112
View Paper titled, Study on Requirements to be Fulfilled With Rules for Repair Replacement Activities in JSME Code on Fitness-for-Service
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Topics: Fitness-for-service, JSME Standards, Maintenance, Inspection, Japan Society of Mechanical Engineers, Flow (Dynamics), In-service inspection
Proceedings Papers

Industry Practice for the Neutron Irradiation Embrittlement of Reactor Pressure Vessel Steels in Japan

Norimichi Yamashita, Masanobu Iwasaki, Koji Dozaki, Naoki Soneda
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 431-439, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75322
https://doi.org/10.1115/ICONE17-75322
View Paper titled, Industry Practice for the Neutron Irradiation Embrittlement of Reactor Pressure Vessel Steels in Japan
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Topics: Embrittlement, Irradiation (Radiation exposure), Neutrons, Reactor vessels, Steel, Surveillance, Boiling water reactors, Electromagnetic scattering, Fracture toughness, Nuclear power stations
Proceedings Papers

An Approach to Controlling Inaccessible Regions for Inspection Defined by Rules on Fitness-For-Service in Japan

Takashi Ota, Koji Dozaki
Proc. ASME. ICONE17, Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition, 155-158, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75585
https://doi.org/10.1115/ICONE17-75585
View Paper titled, An Approach to Controlling Inaccessible Regions for Inspection Defined by Rules on Fitness-For-Service in Japan
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Topics: Fitness-for-service, Inspection, Boilers, Fracture (Materials), Metals, Nozzles, Nuclear industry, Nuclear power stations, Pipes, Safety
Proceedings Papers

Challenges and Status of Development of Inspection Rules in Japanese Fitness-for-Service (FFS) Code

Koji Dozaki
Proc. ASME. PVP2008, Volume 1: Codes and Standards, 547-551, July 27–31, 2008
Publisher: American Society of Mechanical Engineers
Paper No: PVP2008-61255
https://doi.org/10.1115/PVP2008-61255
View Paper titled, Challenges and Status of Development of Inspection Rules in Japanese Fitness-for-Service (FFS) Code
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Topics: Fitness-for-service, Inspection, Damage, Japan Society of Mechanical Engineers, In-service inspection, Maintenance, Pressure, Stress corrosion cracking
Proceedings Papers

Experimental Study on Structural Integrity of a Core Shroud Support with a Crack Under Seismic Load

Shunsuke Okita, Koichi Saito, Koji Dozaki, Akihiro Shima
Proc. ASME. ICONE14, Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy, 161-166, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89378
https://doi.org/10.1115/ICONE14-89378
View Paper titled, Experimental Study on Structural Integrity of a Core Shroud Support with a Crack Under Seismic Load
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Topics: Fracture (Materials), Stress, Boiling water reactors, Finite element methods, Collapse
Proceedings Papers

In-Pile SCC Growth Behavior of Type 304 Stainless Steel in High Temperature Water at JMTR

Yoshiyuki Kaji, Hirokazu Ugachi, Takashi Tsukada, Yoshinori Matsui, Masao Ohmi, Nobuaki Nagata, Koji Dozaki, Hideki Takiguchi
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, 483-489, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89338
https://doi.org/10.1115/ICONE14-89338
View Paper titled, In-Pile SCC Growth Behavior of Type 304 Stainless Steel in High Temperature Water at JMTR
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Topics: High temperature, Stainless steel, Water, Irradiation (Radiation exposure), Neutrons, Boiling water reactors, Fluence (Radiation measurement), Light water reactors, Stress, Testing
Proceedings Papers

SCC in Shroud Support Cylinder Vertical Weld Lines (Tokai-2)

Yuichi Arita, Koji Dozaki, Fumio Manabe, Satoshi Kanno
Proc. ASME. ICONE14, Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy, 119-122, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89345
https://doi.org/10.1115/ICONE14-89345
View Paper titled, SCC in Shroud Support Cylinder Vertical Weld Lines (Tokai-2)
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Topics: Cylinders, Fracture (Materials), Stress, Alloys, Boiling water reactors, Finite element methods, Collapse, Corners (Structural elements), Design, Hoop stress
Proceedings Papers

Development of System Based Code for Structural Integrity of FBRS

Tai Asayama, Masaki Morishita, Nobuchika Kawasaki, Koji Dozaki
Proc. ASME. PVP2002, Pressure Vessel and Piping Codes and Standards, 265-272, August 5–9, 2002
Publisher: American Society of Mechanical Engineers
Paper No: PVP2002-1241
https://doi.org/10.1115/PVP2002-1241
View Paper titled, Development of System Based Code for Structural Integrity of FBRS
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Topics: Breeder reactors, Control characters, Design, Engineering instruments, Engineering standards, Failure, In-service inspection, Inspection, Maintenance, Manufacturing