管道连接装配型ITER增强热负荷第一壁的热工水力分析  

Thermal hydraulic analysis for ITER enhanced heat flux first wall of pipe joint assembly type

作　　者：吴晶 谌继明[1] 王平怀[1] 王正裕 康伟山[1] 高翚[1] WU Jing;CHEN Ji-ming;WANG Ping-huai;WANG Zheng-yu;KANG Wei-shan;GAO Hui(Southwestern Institute of Physics,Chengdu 610041;Chengdu Youfang Ltd.Inc,Chengdu 610041)

机构地区：[1]核工业西南物理研究院,成都610041 [2]成都优仿科技有限公司,成都610041

出　　处：《核聚变与等离子体物理》2022年第1期28-34,共7页Nuclear Fusion and Plasma Physics

摘　　要：对管道连接装配型ITER增强热负荷第一壁(EHF FW)的标准手指对、边缘手指对及中心梁(CB)开展了热工水力分析。分析结果显示流速分布合理,低于1m·s^(-1)或高于10m·s^(-1)的区域非常小;手指对间的流量分配较合理;整个第一壁的压降为0.351MPa,小于0.4MPa的限定值;在8个循环周期内CB最高温度为409.21℃,低于450℃的允许值;而边缘手指铠甲上尖角区域最高温度为846.54℃,需高热负荷实验来验证其安全性。Thermal hydraulic analysis for ITER enhanced heat flux(EHF) first wall(FW) of standard finger pair, edge finger pair and central beam(CB) of pipe joint assembly type is carried out. Analysis results show that the velocity distribution is reasonable and regions where coolant velocity is lower than 1 m·s^(-1) or higher than 10m·s^(-1) are very small, mass flow distribution between finger pairs is rather reasonable, and the pressure drop for whole EHF FW is 0.351 MPa lower than 0.4 MPa, the limited value. The maximum temperature of CB during 8 burn and dwell cycles is about 409.21℃ within the allowable value of 450℃, however, the highest temperature in the sharp corner region of beryllium armor on the edge finger is 846.54℃, which requires high heat load experiment to verify its safety.

关 键 词：ITER 增强热负荷第一壁 热工水力分析 

分 类 号：TL626[核科学技术—核技术及应用]