摘要
CFETR is the ＂ITER-like＂ China fusion engineering test reactor. The design of the breeding blanket is one of the key issues in achieving the required tritium breeding radio for the self-sufficiency of tritium as a fuel. As one option, a BIT （breeder insider tube） type helium cooled ceramic breeder blanket （HCCB） was designed. This paper presents the design of the BIT-HCCB blanket configuration inside a reactor and its structure, along with neutronics, thermo-hydraulics and thermal stress analyses. Such preliminary performance analyses indicate that the design satisfies the requirements and the material allowable limits.
CFETR is the ＂ITER-like＂ China fusion engineering test reactor. The design of the breeding blanket is one of the key issues in achieving the required tritium breeding radio for the self-sufficiency of tritium as a fuel. As one option, a BIT （breeder insider tube） type helium cooled ceramic breeder blanket （HCCB） was designed. This paper presents the design of the BIT-HCCB blanket configuration inside a reactor and its structure, along with neutronics, thermo-hydraulics and thermal stress analyses. Such preliminary performance analyses indicate that the design satisfies the requirements and the material allowable limits.
基金
supported by National Natural Science Foundation of China(Nos.10975157 and 11175207)
the National Magnetic Confinement Fusion Science Program of China(Nos.2013GB108004 and 2011GB114003)
