高氚增殖比包层的设计及热工水力分析  

Design and Thermal-hydraulic Analysis of High Breeding Ratio Blanket

作　　者：王少华[1] 郭海兵[1] 马纪敏[1] 刘志勇[1] 曾和荣[1] 丁文杰[1] 黄洪文[1] 

机构地区：[1]中国工程物理研究院核物理与化学研究所,四川绵阳621900

出　　处：《原子能科学技术》2017年第12期2125-2131,共7页Atomic Energy Science and Technology

基　　金：国家磁约束核聚变能发展研究专项资助(2015GB108003)

摘　　要：本文设计了一种高氚增殖比包层(HBRB),该包层采用多孔U-10Zr合金作为中子倍增剂,Li4SiO4球床作为增殖剂,低活化马氏体(RAFM)钢作为结构材料。在详细研究包层加工工艺、流量分配、中子性能等问题的基础上,完成了包层内部详细结构设计。利用中子学软件分析计算了包层的氚增殖比(TBR)和热沉积分布,并根据计算结果对包层进行热力耦合分析。结果表明:包层TBR较高,且核性能稳定;冷却剂的流量分配情况和压降合理;包层内各组件冷却充分,温度和结构材料热应力不超过限值。A high breeding ratio blanket （HBRB） was designed with porous U-10Zr alloy as neutron multiplier, Li4Si04 pebble bed as tritium breeder, RAFM steel as struc-ture material respectively. Detailed internal structure was developed with consideration of fabrication procedure,flow rate distribution and neutron performance. The tritium breeding ratio （TBR） and distribution of heat deposition were calculated, and the thermal-hydraulic analyses of the HBRB combining with results of neutronics calculation were also carried out. The results show that the TBR is high enough and the neutronics performance is stable. The coolant flow rate distribution and pressure drop are reasona-ble. The maximum blanket component temperature and thermal stress are lower than critical values.

关 键 词：氚增值比 聚变包层 热工水力分析 U-10Zr 

分 类 号：TL33[核科学技术—核技术及应用]