Abstract
Full tungsten divertor is employed for ITER, and the tungsten will be the most potential candidate for the surface material of plasma facing components in fusion reactor after DEMO. Under a Broader Approach (BA) activity, a satellite tokamak device JT-60SA is expected to contribute the investigation of many factors and issues related to the fusion plasma and components. JT-60SA has a future plan to transfer the surface of plasma facing components from carbon fiber reinforced carbon composite (CFC) to tungsten, and investigate the interaction of plasma and tungsten. For this plan, joining and coating technologies of tungsten on CFC is an important issue. Present research developed a fabrication method of the W/CFC clad plates and investigated the mechanical, microstructural and thermal properties of them.
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