2016 Annual Meeting

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Oral Presentation

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

[1H09-13] SiC-2

Sat. Mar 26, 2016 2:45 PM - 4:05 PM Room H (Lecture Rooms B B204)

Chair: Akira Hasegawa (Tohoku Univ.)

3:45 PM - 4:00 PM

[1H13] Radiation damage analysis of high purity SiC by TEM

＊Mohd Idzat Idris1, Toyohiko Yano1, Katsumi Yoshida1 (1.Tokyo Institute of Technology)

Keywords:Silicon carbide, Radiation damage, TEM

SiC is a well-known material that has been used in nuclear application due to its excellent mechanical and chemical properties. Exposure to neutron irradiation will degrade the propeties through displacement or transmutation effects. Thus, radiation damage microsturcture in SiC need to be determined by TEM.