日本原子力学会 2014年春の年会

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IV. 核燃料サイクルと材料 » 402-1 炉材料とその照射挙動

[F15-16] SiC/SiC複合材料2

Wed. Mar 26, 2014 4:05 PM - 4:40 PM F (1号館 11C)

座長:藪内聖皓(東大)

[F15] Neutron Irradiation Swelling of SiC and SiC/SiC at Low Dose/Temperature

bin Idris Mohd Idzat1 (1.Researh Laboratory for Nuclear Reactors)

抄録
Silicon carbide (SiC) is used as a layer in TRISO fuel of high temperature gas-cooled reactors because of its excellent thermal and mechanical properties. SiC fiber-reinforced SiC composites (SiCf/SiC) are also a candidate material for structural material for fusion reactor blanket and cladding materials of advance fission reactors. In this research, seven of SiC or SiCf/SiC composites specimens with different fabrication processes were irradiated in the BR2 Rreactor up to a fluence of 2.0-2.5×1024 (E>0.1 MeV) at 60-90oC