Strategy Study and Preliminary Conceptual Design of the Remote Maintenance Systems for in Vessel Components of CFETR

The design work of China Fusion Engineering Test Reactor (CFETR) has been started since 2012. In past years, the physical parameters and related engineering design of subsystems were modified, evaluated and redesigned for several rounds in order to fulfill the final scientific goals. Remote maintenance (RM) is identified as one of the key issues of the CFETR because of the neutron activation of the in-vessel components. Different schemes were proposed and comparatively assessed to reach the best possible tradeoff between RM strategies and Tokamak machine designs. This paper will give an overall introduction of the latest version of RM strategy and system conceptual design based on current physical configuration with 16 toroidal field coils and larger sizes. In general, modular blanket components will be removed through only two large vertical maintenance ports while two lower horizontal ports are employed for divertor removing. The work has also provided guidelines for compatibility consideration such as the blanket and divertor modularity, the cryostat pipe arrangement, and the corridor layout to hot cell. In addition, some innovative RM system design for the blanket and divertor maintenance was also provided in the paper, such as the implementation of a toroidal mover transferring blankets to vertical ports, and the novel cask design ensuring storing six divertor at the same time.