Shigeru Takaya

发表

Creep-Fatigue Evaluation Methodologies and Related Issues for Japan Sodium Cooled Fast Reactor (JSFR)☆

Tai Asayama, Shigeru Takaya, Yuji Nagae, 2013 .

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

Masaaki Tanaka, Shigeru Takaya, Tatsuya Fujisaki, 2015 .

Determination of in-service inspection requirements for fast reactor components using System Based Code concept

Tai Asayama, Shigeru Takaya, Hideo Machida, 2016 .

Elaboration of the System Based Code Concept — Activities in JSME and ASME: (3) Guidelines on Structural Reliability Evaluation for FBR

Shigeru Takaya, Hideo Machida, Yoshio Kamishima, 2014 .

Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (4) Creep–Fatigue Evaluation Method for Modified 9Cr–1Mo Steel

Tai Asayama, Shigeru Takaya, Yuji Nagae, 2013 .

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

Tai Asayama, Shigeru Takaya, 2016 .

Load and resistance factor design approach for seismic buckling of fast reactor vessels

Tai Asayama, Shigeru Takaya, Yoshio Kamishima, 2017 .

Development of System Based Code: Part 2—Application of Reliability Target for Configuration of ISI Request

Tai Asayama, Shigeru Takaya, Satoshi Okajima, 2010 .

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

Tai Asayama, Shigeru Takaya, Yuji Nagae, 2015 .

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

Tai Asayama, Shigeru Takaya, Yoshio Kamishima, 2016 .

Development of Structural Codes for JSFR Based on the System Based Code Concept

Tai Asayama, Masaki Morishita, Shigeru Takaya, 2014 .

Creep–fatigue evaluation method for weld joints of Mod.9Cr–1Mo steel. Part I: Proposal of the evaluation method based on finite element analysis and uniaxial testing

Shigeru Takaya, Masanori Ando, M. Ando, 2017 .

Development of Limit State Design for Fast Reactor by System Based Code

Tai Asayama, Shigeru Takaya, Hideo Machida, 2013 .

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

Kenichi Kurisaka, Tai Asayama, Shigeru Takaya, 2013 .

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, 2014 .

Application of the System Based Code Concept to the ASME Code for Liquid Metal Reactors

Tai Asayama, Shigeru Takaya, Masaki Morishita, 2012 .

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

Kenichi Kurisaka, Tai Asayama, Shigeru Takaya, 2015 .

Reconstruction of Magnetic Moments Distribution from 2D Scan Data using Neural Networks

Kazuyuki Demachi, Shigeru Takaya, Kenzo Miya, 1999 .

302 Development of Integrated Numerical Analysis Model for Unsteady Phenomena in Upper Plenum and Hot-Leg Piping System of JSFR

Masaaki Tanaka, Shigeru Takaya, Tatsuya Fujisaki, 2014 .

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

Tai Asayama, Shigeru Takaya, Shigeru Takaya, 2015 .

Application of magnetic phenomena to analysis of stress corrosion cracking in welded part of stainless steel

Shigeru Takaya, Kenzo Miya, 2005 .

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

Tai Asayama, Shigeru Takaya, Yuji Nagae, 2013 .

Corrosion resistance of Al-alloying high Cr–ODS steels in stagnant lead–bismuth

Shigeru Takaya, Tomohiro Furukawa, Masaki Inoue, 2010 .

Estimation of stress corrosion cracking sensitivity of type 304 stainless steel by magnetic force microscope

Kazuyuki Demachi, Shigeru Takaya, Mitsuru Uesaka, 2004 .

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

Shigeru Takaya, 2014 .

Proposal on LBB evaluation conditions for sodium cooled fast reactor pipes and effects of pipe parameters

Shigeru Takaya, Hiroki Yada, Hideo Machida, 2017 .

Development of a magnetic sensor system for predictive IASCC diagnosis on stainless steels in a nuclear reactor

Shigeru Takaya, Tetsuya Uchimoto, Takashi Tsukada, 2011 .

Nondestructive evaluation of neutron irradiation damage on type 316 stainless steel by measurement of magnetic properties

Shigeru Takaya, Yuji Nagae, Kazumi Aoto, 2010 .