Speaker
Description
Design and development activities are currently underway with the aim of demonstrating power generation using a Fusion DEMO reactor in Japan in the 2030s. At QST Rokkasho, feasibility studies are being conducted on a fusion neutron source required for qualifying blanket performance for the Fusion DEMO reactor (hereafter referred to as DEMO-FNS).
Unlike A-FNS [1], DEMO-FNS is planned to operate in a pulsed mode with a duty cycle of several tens of percent, rather than in continuous-wave operation for the deuteron beam current. The nominal beam energy and beam cur-rent are assumed to be approximately 40 MeV and 50 mA, respectively.
In A-FNS, liquid lithium was adopted as the target material from the viewpoint of heat removal. In contrast, DEMO-FNS is investigating high–melting-point metals, with beryllium currently considered a promising candidate. In this presentation, we report on studies of a beryllium target for DEMO-FNS, including neutron yield evaluation, thermal analysis, structural strength assessment, and mitigation strategies for blistering.