聚变增殖堆液态金属Li自冷包层的热工水力分析

THERMAL HYDRAULIC ANALYSES OF LIQUID LITHIUM SELF-COOLED BLANKET FOR A FUSION BREEDER

完成了托卡马克商用混合堆 TCB(Tokamak Commercial Breeder)Li 自冷包层设计的热工水力分析,讨论了热工水力设计中的一些关键问题。用两维有限元热传导程序 AYER 计算了 TCB 包层的温度分布,用液态金属 MHD(Magnetohydraudynamic)压降公式计算了包层的压降。同时,还分析了包层冷却剂丧失事故 LOCA 的瞬态热工过程。分析表明,正常工况下,包层结构材料最高温度,结构材料与冷却剂界面最高温度,以及包层总压降都满足堆设计要求。在 LOCA 工况下,如果停堆后1小时内包层中的燃料球能够借助重力卸出包层,第一壁和包层是安全的,并且不会受到损伤。

The thermal hydraulic analyses of a liquid lithium self-cooled blanket for a tokamak commer- cial breeder,TCB,[1]have been performed.Some critical thermal hydraulic design issues are discussed.The temperature distribution in the TCB blanket is calculated using a two dimensional finite-element heat transport code AYER,[2]and the prssure drop is computed using several sets of liquid metal magnetohydraudynamic(MHD)pressure drop formulae.Also,the analysis of transient thermal process in the blanket after a loss-of-coolant accident(LOCA)has been made. It is found that,for normal conditions,the peak structural material temperature,the peak structure/coolant interface temperature and the total pressure drop of the blanket can all satisfy the reactor design requirements.Under LOCA conditions,the first wall and the blanket are found to be safe and free from damage if the fuel balls in the blanket are dumped by gravity within 1 hour after the reactor shutdown.