摘要
The water-cooled ceramic breeder blanket（WCCB） is one of the blanket candidates for China fusion engineering test reactor（CFETR）.In order to improve power generation efficiency and tritium breeding ratio,WCCB with superheated steam is under development.The thermal-hydraulic design is the key to achieve the purpose of safe heat removal and efficient power generation under normal and partial loading operation conditions.In this paper,the coolant flow scheme was designed and one self-developed analytical program was developed,based on a theoretical heat transfer model and empirical correlations.Employing this program,the design and analysis of related thermal-hydraulic parameters were performed under different fusion power conditions.The results indicated that the superheated steam water-cooled blanket is feasible.
The water-cooled ceramic breeder blanket（WCCB） is one of the blanket candidates for China fusion engineering test reactor（CFETR）.In order to improve power generation efficiency and tritium breeding ratio,WCCB with superheated steam is under development.The thermal-hydraulic design is the key to achieve the purpose of safe heat removal and efficient power generation under normal and partial loading operation conditions.In this paper,the coolant flow scheme was designed and one self-developed analytical program was developed,based on a theoretical heat transfer model and empirical correlations.Employing this program,the design and analysis of related thermal-hydraulic parameters were performed under different fusion power conditions.The results indicated that the superheated steam water-cooled blanket is feasible.
基金
supported by the National Special Project for Magnetic Confined Nuclear Fusion Energy of China(Nos.2013GB108004,2014GB122000 and 2014GB119000)
National Natural Science Foundation of China(No.11175207)
