摘要
TOPAZⅡ是用于为空间探索提供动力的一种反应堆,TOPAZⅡ堆本体内涉及液态钠钾合金流动,流体和冷却剂套管之间的换热、堆本体零部件的固体导热,反射层外壁面与外界的辐射换热等问题,本文利用计算流体力学程序CFX对TOPAZⅡ反应堆堆本体流固共轭传热进行数值模拟,数值模拟计算得到了全堆芯的流量分配数据,数据表明各通道流量分配因子偏差非常小;得到了活性区环形通道的壁面摩擦系数,摩擦系数反映了压降与流量的关系,与经验关系式计算得到的摩擦系数进行了对比,额定流量下的数值结果与经验关系式的偏差不到5%;数值模拟得到的努赛尔数与已发表的经验关系式进行了比较,最大偏差小于1%,验证了液态钠钾合金环管内的流动与换热数值模拟的可靠性与准确性。计算得到了详细的活性区慢化剂、端部铍反射层、侧铍反射层等的温度分布,所获得的计算结果可以为力学分析提供设计依据。
TOPAZ Ⅱ,cooled by liquid metal,moderated by ZrH8,reflected by Be,is a reactor used for deep space exploring.In TOPAZ Ⅱ reactor complex,there exists liquid metal flowing and heat transfer in annular channels,thermal conduction in the solid components,and thermal radiation between the outside wall of the reflector and the surrounding environment.The mature fluid computational dynamics software CFX was used to perform the numerical simulation of conjugate heat transfer in TOPAZ-Ⅱreactor complex.And the calculated mass flow factors of all the coolant channels have shown a great uniform distribution tendency.The friction factor,reflecting the relationship between the pressure drop and the mass flow rate,was obtained through CFDPOST, which have been validated against that calculated with empirical correlations.The comparison has shown that numerically calculated friction factors under nominal flow condition were less then 5% deviation from empirical ones.The Nusselt numbers,reflecting the heat transfer performance,were also acquired through CFD-POST,and compared with that calculated empirically by correlations reported in the reference papers.And the results have shown a great agreement with less then 1%deviation from each other.Thus the flow and heat transfer numerical simulation were reliable and accurate.The numerical simulation gave detailed three dimensional temperature field in related solids,which provided input for the mechanical analysis and lay foundation for thermal hydraulic optimization of this type of reactor.
作者
邹佳讯
郭春秋
孙征
ZOU Jiaxun;GUO Chunqiu;Sun Zheng(Reactor Engineering Technology Research Division,China Institute of Atomic Energy,Beijing 102413,China)
出处
《核科学与工程》
CAS
CSCD
北大核心
2020年第6期1104-1112,共9页
Nuclear Science and Engineering
作者简介
邹佳讯(1983-),男,安徽人,副研究员,硕士研究生,现主要核能科学与工程方面研究。
