Conceptual design of the supercritical CO2 cooled lithium lead blanket for CFETR

A conceptual design of the supercritical CO2 cOoled Lithium-Lead (COOL) blanket has been proposed as one advanced blanket candidate for the Chinese Fusion Engineering Testing Reactor (CFETR). At present, the COOL blanket is designed to fulfill the requirement of operating under the fusion power of 1.5 GW of CFETR while realizing the tritium self-sufficiency. Structural designs are carried out for outboard and inboard blanket segments and analyses with regard to neutronics and thermo-hydraulics are conducted to evaluate the blanket performance. Results indicate that a comparatively high Tritium Breeding Ratio (TBR) of 1.183 and a PbLi outlet temperature of 600 – 700◦C can be achieved for this blanket concept. Besides, a Power Conversion System (PCS) based on the supercritical CO2 recompressing cycle is preliminarily designed for the blanket and the gross thermal efficiency is estimated to be 39% – 46% when assuming the turbine inlet temperature ranges between 550◦C and 650◦C.

超临界二氧化碳冷却锂铅（COOL）包层的概念设计已被提出作为中国聚变工程试验堆（CFETR）的先进包层候选方案之一。目前，COOL包层的设计旨在满足CFETR在1.5 GW聚变功率下运行的需求，同时实现氚自给自足。针对内外包层段开展了结构设计，并通过中子学与热工水力分析评估包层性能。结果表明，该包层概念可实现1.183的较高氚增殖比（TBR）及600–700℃的铅锂出口温度。此外，基于超临界二氧化碳再压缩循环的动力转换系统（PCS）已初步为该包层完成设计；假设涡轮进口温度处于550–650℃范围，其总热效率预计可达39%–46%。