Presentation Information
[2B06]Development of Tungsten Boride Cermet for Radiation Shielding Material in Fusion Reactor
*Kaiji Yamamura1, Yasuyuki ogino1, Yuki Jimba1, Hao Yu1, Sosuke kondo1, Ryuta Kasada1 (1. Tohoku Univ.)
Keywords:
Radiation shielding,Tungsten boride,Structural material for fusiton reactor
Tungsten boride (WB) has high neutron and gamma-ray shielding performance. Therefore, it is expected to be used as a radiation shielding material for spherical tokamak, which has limited space for installing material to protect the central superconducting coil. However, WB has a low sinterability, thermal properties, and fracture toughness. So, it is necessary to improve these properties.
In this study, we fabricated WB cermet by adding Cu, aiming to elucidate the effect of Cu addition the sinterability, thermal properties, and fracture toughness of WB.
WB-Cu cermet sintered via PECS demonstrates superior sintered density, thermal diffusivity, and fracture toughness to monolithic WB. This suggests that cermet is an effective means to improve sinterability, thermal properties, and fracture toughness of WB.
In this study, we fabricated WB cermet by adding Cu, aiming to elucidate the effect of Cu addition the sinterability, thermal properties, and fracture toughness of WB.
WB-Cu cermet sintered via PECS demonstrates superior sintered density, thermal diffusivity, and fracture toughness to monolithic WB. This suggests that cermet is an effective means to improve sinterability, thermal properties, and fracture toughness of WB.
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