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

•A conceptual design of the supercritical CO2 cooled Lithium-Lead blanket has been proposed for CFETR.•Structural designs are carried out and analyses of neutronics and thermo-hydraulics are conducted.•Tritium Breeding Ratio of 1.183 and a PbLi outlet temperature of 600–700°C can be achieved.•Gross...

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Published inFusion engineering and design Vol. 173; p. 112800
Main Authors Chen, Lei, Jiang, Kecheng, Ma, Xuebin, Wu, Qiuran, Yu, Yi, Lu, Peng, Cheng, Xiaoman, Chen, Long, Yang, Juancheng, Zhu, Qingjun, Huang, Kai, Zhang, Nianmei, Ni, Ming-Jiu, Liu, Songlin
Format Journal Article
LanguageEnglish
Published Amsterdam Elsevier B.V 01.12.2021
Elsevier Science Ltd
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Summary:•A conceptual design of the supercritical CO2 cooled Lithium-Lead blanket has been proposed for CFETR.•Structural designs are carried out and analyses of neutronics and thermo-hydraulics are conducted.•Tritium Breeding Ratio of 1.183 and a PbLi outlet temperature of 600–700°C can be achieved.•Gross thermal efficiency is estimated to be 39%–46% by using the supercritical CO2 recompressing cycle. 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.
ISSN:0920-3796
1873-7196
DOI:10.1016/j.fusengdes.2021.112800