Yuji Nagae

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 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 .

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

Tai Asayama, Shigeru Takaya, Yuji Nagae, 2015 .

F214 Development of elevated temperature structural design method for fast reactor vessels : Part 1: Concept of development in strength evaluation

Shoichi Kato, Naoto Kasahara, Yuji Nagae, 2008 .

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

Tai Asayama, Masaki Morishita, Shigeru Takaya, 2014 .

Development of a Material Strength Standard for Japanese Demonstration Fast Breeder Reactor

Tai Asayama, Yuji Nagae, Takashi Wakai, 2009 .

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 .

Effect of W on recovery of lath structure during creep of high chromium martensitic steels

Yuji Nagae, Kouichi Maruyama, Y. Nagae, 1999 .

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

Shigeru Takaya, Yuji Nagae, Kazumi Aoto, 2010 .

An experimental study on the correlation of natural magnetization and mechanical damages in an austenitic stainless steel

Yuji Nagae, Kenzo Miya, Zhenmao Chen, 2002 .

Evaluation of creep–fatigue life based on fracture energy for modified 9Cr–1Mo steel

Yuji Nagae, Y. Nagae, 2013 .

Creep Strength Evaluation of Welded Joint Made of Modified 9Cr-1Mo Steel for Japanese Sodium Cooled Fast Reactor (JSFR)

Tai Asayama, Yuji Nagae, Takashi Wakai, 2010 .