ITER屏蔽包层模块的热工水力与热应力分析  

Thermal hydraulic performance and structural thermal stress analysis for ITER shield blanket module

作　　者：康伟山[1] 张斧[1] 吴继红[1] 许增裕[1] 

机构地区：[1]核工业西南物理研究院,成都610041

出　　处：《核聚变与等离子体物理》2007年第4期320-323,共4页Nuclear Fusion and Plasma Physics

摘　　要：对ITER靠近中性束端口的标准屏蔽包层模块进行了热工水力与热应力计算与分析。首先用流体力学方法计算了两种导流管的阻力系数,然后通过合理简化计算了冷却管道系统的水力学,最后根据水力学的计算结果得到温度及应力的分布。分析结果表明,现有的屏蔽包层设计与旧的设计相比,能更有效地降低能量损失、提高冷却效率,满足设计要求。同时需要做局部改进,以确保安全运行。Hydraulic and thermal analyses of the shield block have been done to examine whether the current design meets the 1TER requirements or not. Firstly, the loss coefficient in the flow driver was calculated from individual analysis with CFD code. Then, the pressure drop, velocity and heat transfer coefficient were obtained in the cooling system through a optirnised model. Finally, the thermal analysis was carded out based on the hydraulic results with FEM code to examine the distribution of temperature and thermal stress. The analysis results show that the current design is more efficient to reduce the energy loss and improve the cooling efficiency, and satisfy the ITER requirements. Of course, further optimisation or improvement is still needed to ensure safety operation.

关 键 词：ITER 屏蔽包层 热工水力学 计算流体力学 有限元法 

分 类 号：TL627[核科学技术—核技术及应用]