Conceptual Design of CFETR Divertor Dome for Remote Handling

The design of the China Fusion Engineering Test Reactor (CFETR) device is one of the main tasks in the next stage of research on fusion energy in China. The CFETR divertor is a key in-vessel plasma-facing component, which will suffer from sputtering erosion and exfoliation caused by intense plasma bombardment, severe heat fluxes, and neutron irradiation. Due to neutron activation of in-vessel components, remote handling (RH) technology has been considered as one of the essential issues of the CFETR divertor. In this article, a new concept of an integral hybrid divertor blanket for the CFETR is proposed, which is feasible for installation and disassembly in CFETR vacuum vessel by RH. Dome is an important part of the CFETR divertor, which comprises 80 modules, and each module is composed of flat-type plasma-facing units (PFUs), steel supports (SSs), and RH compatible structures. Every Dome module is connected to the CFETR blanket by RH compatible structures. This article mainly carries out the conceptual design of Dome (option), degree of freedom (DOF) analysis, stability analysis, RH process planning, and flow field analysis of cooling scheme, which will provide a solid foundation for its subsequent thermal-hydraulic analysis.