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Proceedings Papers

Proposal of Simplified J-Integral Evaluation Method for a Through Wall Crack in SFR Pipe Made of Mod.9Cr-1Mo Steel

Takashi Wakai, Hideo Machida, Manabu Arakawa, Koichi Kikuchi
Proc. ASME. ETAM2018, ASME 2018 Symposium on Elevated Temperature Application of Materials for Fossil, Nuclear, and Petrochemical Industries, V001T03A001, April 3–5, 2018
Paper No: ETAM2018-6708
DOI: https://doi.org/10.1115/ETAM2018-6708
View Paper titled, Proposal of Simplified J-Integral Evaluation Method for a Through Wall Crack in SFR Pipe Made of Mod.9Cr-1Mo Steel
Open the PDF for Proposal of Simplified J-Integral Evaluation Method for a Through Wall Crack in SFR Pipe Made of Mod.9Cr-1Mo Steel in another window
Topics: Evaluation methods, Fracture (Materials), Pipes, Sodium fast reactors, Steel, Finite element analysis, Stress, Failure analysis, Coolants, Cylinders
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
View Paper titled, 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
Open the PDF for 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 in another window
Topics: Construction, Design, Fast neutron reactors, JSME Standards, Japan Society of Mechanical Engineers, Creep, Damage, Fatigue, Finite element analysis, Materials properties
Proceedings Papers

A Study for Proposal of Welded Joint Strength Reduction Factors of Modified 9Cr-1Mo Steel for Japan Sodium Cooled Fast Reactor (JSFR)

Takashi Wakai, Takashi Onizawa, Takehiko Kato, Shingo Date, Koichi Kikuchi, Kenichiro Satoh
Proc. ASME. PVP2013, Volume 3: Design and Analysis, V003T03A105, July 14–18, 2013
Paper No: PVP2013-97091
DOI: https://doi.org/10.1115/PVP2013-97091
View Paper titled, A Study for Proposal of Welded Joint Strength Reduction Factors of Modified 9Cr-1Mo Steel for Japan Sodium Cooled Fast Reactor (JSFR)
Open the PDF for A Study for Proposal of Welded Joint Strength Reduction Factors of Modified 9Cr-1Mo Steel for Japan Sodium Cooled Fast Reactor (JSFR) in another window
Topics: Sodium fast reactors, Steel, Welded joints, Creep, Rupture, Stress, Base metals, Design, Temperature, Damage
Proceedings Papers

A Study on Fatigue and Creep-Fatigue Life Assessment Using Cyclic Thermal Tests With Mod.9Cr-1Mo Steel Structures

Masanori Ando, Hiroshi Kanasaki, Shingo Date, Koichi Kikuchi, Kenichiro Satoh, Hideki Takasho, Kazuyuki Tsukimori
Proc. ASME. PVP2012, Volume 6: Materials and Fabrication, Parts A and B, 327-336, July 15–19, 2012
Paper No: PVP2012-78402
DOI: https://doi.org/10.1115/PVP2012-78402
View Paper titled, A Study on Fatigue and Creep-Fatigue Life Assessment Using Cyclic Thermal Tests With Mod.9Cr-1Mo Steel Structures
Open the PDF for A Study on Fatigue and Creep-Fatigue Life Assessment Using Cyclic Thermal Tests With Mod.9Cr-1Mo Steel Structures in another window
Topics: Creep, Fatigue, Steel, Finite element analysis, Failure, Fracture (Materials), Temperature, Temperature distribution, Cooling, Cycles
Proceedings Papers

Development of LBB Assessment Method for Japan Sodium Cooled Fast Reactor (JSFR) Pipes (4): Verification of Crack Opening Displacement Assessment Method for Thin Wall Pipes Made of Mod.9Cr-1Mo Steel

Takashi Wakai, Hideo Machida, Shinji Yoshida, Fumiko Kawashima, Koichi Kikuchi, Yang Xu, Kazuyuki Tsukimori
Proc. ASME. PVP2011, Volume 6: Materials and Fabrication, Parts A and B, 705-714, July 17–21, 2011
Paper No: PVP2011-57507
DOI: https://doi.org/10.1115/PVP2011-57507
View Paper titled, Development of LBB Assessment Method for Japan Sodium Cooled Fast Reactor (JSFR) Pipes (4): Verification of Crack Opening Displacement Assessment Method for Thin Wall Pipes Made of Mod.9Cr-1Mo Steel
Open the PDF for Development of LBB Assessment Method for Japan Sodium Cooled Fast Reactor (JSFR) Pipes (4): Verification of Crack Opening Displacement Assessment Method for Thin Wall Pipes Made of Mod.9Cr-1Mo Steel in another window
Topics: Displacement, Fracture (Materials), Pipes, Sodium fast reactors, Steel, Thin wall structures, Leakage, Sodium, Work hardening, Coolants
Proceedings Papers

Development of LBB Assessment Method for Japan Sodium Cooled Fast Reactor (JSFR) Pipes (5): Crack Growth Assessment Method for Pipes Made of Mod.9Cr-1Mo Steel

Takashi Wakai, Hideo Machida, Shinji Yoshida, Takumi Tokiyoshi, Koichi Kikuchi, Yang Xu, Kazuyuki Tsukimori
Proc. ASME. PVP2011, Volume 6: Materials and Fabrication, Parts A and B, 715-722, July 17–21, 2011
Paper No: PVP2011-57513
DOI: https://doi.org/10.1115/PVP2011-57513
View Paper titled, Development of LBB Assessment Method for Japan Sodium Cooled Fast Reactor (JSFR) Pipes (5): Crack Growth Assessment Method for Pipes Made of Mod.9Cr-1Mo Steel
Open the PDF for Development of LBB Assessment Method for Japan Sodium Cooled Fast Reactor (JSFR) Pipes (5): Crack Growth Assessment Method for Pipes Made of Mod.9Cr-1Mo Steel in another window
Topics: Fracture (Materials), Pipes, Sodium fast reactors, Steel, Creep, Fatigue cracks, Thin wall structures, Displacement, Fatigue, Geometry