[F15] Swelling of SiC and SiCf/SiC after Neutron Irradiation at Lower Temperature
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
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