Neutron Irradiation Swelling of SiC and SiC f /SiC for Advanced Nuclear Applications

作     者：Mohd Idzat Idris Hiroshi Konishi Masamitsu Imai Katsumi Yoshida Toyohiko Yano 

作者机构：Department of Nuclear Engineering Graduate School of Science and Engineering Tokyo Institute of Technology 2-12-1 Ookayama Meguro-ku Tokyo 152-8550 Japan The National University of Malaysia School of Applied Physics Faculty of Science and Technology 43600 Bangi Selangor Malaysia Research Laboratory for Nuclear Reactors Tokyo Institute of Technology 2-12-1 Ookayama Meguro-ku Tokyo 152-8550 Japan 

出 版 物：《Energy Procedia》 

年 卷 期：2015年第71卷

页      面：328-336页

主　　题：Radiation swelling Silicon carbide SiC f /SiC Neutron irradiation 

摘      要：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 (SiC f /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 monolithic SiC or SiC f /SiC composites materials with different fabrication processes were irradiated in the BR2 reactor up to a fluence of 2.0-2.5×10 24 (E0.1 MeV) at 333-363 K. Changes in macroscopic lengths and lattice parameters before and after the neutron irradiation were measured. Furthermore, microstructure of SiC f /SiC composites was investigated using a scanning electron microscope, too. Results showed that after the neutron irradiation, the group of SiC and SiC f /SiC composites were swelled approximately 1.24∼1.33% and 1.00∼1.19% in length, respectively. Apparently the presence of fibers resulted in smaller swelling. It may be attributed for smaller swelling of SiC fibers. Further difference in swelling may be caused by the presence of different sintering additives.