中国铅基研究实验堆绕丝燃料组件热工水力分析  

Thermal-hydraulic Analysis in Wire-wrapped Fuel Assembly for China Lead-based Research Reactor

作　　者：葛增芳[1] 周涛[1] 柏云清[1] 宋勇[1] 

机构地区：[1]中国科学院核能安全技术研究所,中国科学院中子输运理论与辐射安全重点实验室,安徽合肥230031

出　　处：《原子能科学技术》2015年第B05期167-173,共7页Atomic Energy Science and Technology

基　　金：中国科学院战略性先导科技专项资助项目(XDA03040000);加速器驱动次临界堆瞬态安全过程与影响机理研究资助项目(91026004)

摘　　要：在铅基研究反应堆燃料组件设计中,燃料棒之间的绕丝可减少燃料棒在运行过程的机械振动,并使冷却剂在各子通道间有效混合,对绕丝燃料组件内冷却剂的热工水力分析将对燃料组件的设计与优化具有重要意义。本文通过CFD方法对中国铅基研究实验堆(CLEAR-Ⅰ)燃料组件参考设计内的冷却剂流动换热过程进行数值模拟,并分析绕丝组件的速度场、温度场等流场特征量的分布规律。结果表明:绕丝在流场中起着搅混冷却剂的作用,内通道搅混较外通道相对均匀;组件内横向流强度、摩擦系数在入口段先迅速变化,后在充分发展区呈波浪状在其平均值上下波动,努塞尔数变化规律与之类似;包壳最高温度满足安全设计限值。In order to reduce the mechanical vibration of fuel rods during the operation and conduce to the coolant mixing between sub-channels, the fuel assembly of lead- based research reactor was designed by using wire-wrapped fixed structure. While the wire-wrapped structure will influence the coolant flow and heat transfer characteristics inside fuel assembly, it＇s essential to analyze the influence of wire-wrapped structure on the flow and convective heat transfer in the fuel assembly for optimization design of CLEAR- I fuel assembly. In this contribution, fields of velocity, temperature and other flow field characteristics in the wire-wrapped fuel assembly were analyzed using CFD tools. The results show that wire-wraps play an important role on stirring the coolant,and the strength of stirring in inner channel is stronger than in out channel. The friction factor decreases in the entrance region and then attains periodic fluctuations in the fully developed region, and the Nusselt number changes have a same behavior. The cladding highest temperature is under the limit of safety design.

关 键 词：铅基研究反应堆 绕丝 燃料组件 CFD数值分析 

分 类 号：TL334[核科学技术—核技术及应用]