Oral Presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 402-1. Nuclear Materials and the Irradiation Behavior

[2H08-10] Stainless Steels

Sun. Mar 27, 2016 11:15 AM - 12:00 PM Room H (Lecture Rooms B B204)

Chair: Hiroaki Abe (Univ. of Tokyo)

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11:15 AM - 11:30 AM

[2H08] Tensile fracture behavior at grain boundary in neutron-irradiated stainless steels

＊Katsuhiko Fujii¹, Terumitsu Miura¹, Koji Fukuya¹ (1.Institute of Nuclear Safety System)

11:30 AM - 11:45 AM

[2H09] Aging effect on SCC Growth of Cast Austenitic Stainless Steels in High Temperature Water

＊Takuyo Yamada¹, Takumi Terachi¹, Tomoki Miyamoto¹, Koji Arioka¹ (1.Institute of Nuclear Safety System, inc.)

11:45 AM - 12:00 PM

[2H10] A first principle study on the composition deviation of Ni-Si precipitates formed in irradiated stainless steel

＊Dongyue CHEN¹, Kenta MURAKAMI², Naoto SEKIMURA¹ (1.The University of Tokyo, Department of Nuclear Engineering and Management, School of Engineering, 7-3-1 Hongo Bunkyo-ku, Tokyo 113-8656, Japan, 2.The University of Tokyo, Nuclear Professional School, School of Engineering, 2-22 Shirakata-Shirane, Tokai-mura, Ibaraki 319-1188, Japan)