He冷却LLi氚增殖包层的热工水力初步设计

Preliminary Thermal Hydraulic Design for a Helium-Cooled Liquid Lithium Tritium Breeder Blanket

完成了托卡马克工程试验混合堆ＴＥＴＢ－ⅢＨｅ冷液态金属Ｌｉ（ＬＬｉ）氚增殖包层的初步热工水力设计，探讨了包层中载氚的两种可能方式。同时，用程序完成了对第一壁和包层的温度场计算及热工水力设计参数的初步优化。分析结果表明，尽管Ｈｅ气的导热性和密度都比液态金属冷却剂低得多，但仍有可能使堆芯在２．０ＭＰａ的低压下运行，并且包层的热工水力设计参数满足设计要求。

A preliminary thermal-hydraulic design of a helium-cooled liquid lithium (LLi) tritiumbreeder blanket for a Tokamak Engineering Test Breeder, TETB- Ⅲ has been carried out.Two possible schemes of tritium transport in the blanket are discussed. Meanwihie, the temperature field and the optimization of thermal-hydraulic design parameters in the blanket havebeen performed. The results of the analyses show that it is possible to operate the reactor below 2. 0 MPa, and the thermal-hydraulic design parameters can satisfy the reactor design resquirements even though the thermal conductivity and the density of the helium are much lessthan that of liquid metal coolant.