摘要
This paper summarizes the key engineering outcomes from the ARIES-CS study. The most promising power plant concept is described. The engineering design of the fusion power-core components (including the blanket and divertor) and the coil structural design are briefly described along with a summary of the key results from the detailed neutronics, stress, thermal-hydraulic and power cycle analyses performed in support of the design. The preferred port-based maintenance scheme is summarized. The key stellarator-specific challenges affecting the design are highlighted, including the impact of the minimum plasma–coil distance, the coil design requirements and the need for alpha power accommodation.