节点文献
摇摆条件下棒束通道单相核热耦合研究
Research of Nuclear Thermal Coupling for Single-phase Flow in Rod Bundle Channel under Rolling Motion
【Author】 Yang Yu;Pan Liangming;He Hui;School of Power Engineering, Chongqing University;
【机构】 重庆大学动力工程学院;
【摘要】 本文利用Fluent平台,通过用户自定义函数(UDF)接口添加摇摆和核反馈等模块程序,使之能对摇摆条件下单相核热耦合进行模拟。采用实验与理论相结合的方法对摇摆模块进行了验证,并基于已验证的摇摆模块,重点分析摇摆运动对3×3棒束通道及其子通道流动传热的影响;在摇摆的基础上,通过对棒束组件加入核反馈,探求核反馈与摇摆运动的相互关系。结果表明:摇摆运动会降低棒束通道流量,并能增强棒束通道的传热,对于各个子通道的流动传热影响却不尽相同;核反馈对摇摆引起的流量波动具有较小的抑制,并会降低棒束的平均功率。
【Abstract】 Simulation of the nuclear thermal coupling under rolling motion was presented in current paper, and rolling model and nuclear feedback module were appied to Fluent code by mean of UDF. The experimental data and theoretical analysis were used to validate the rolling model, the results to be shown in the paper indicated that rolling model could predict the flow rate and heat transfer in rolling motion with satisfactorily agreements. Therefore, the rolling model was then extrapolated to a 3×3 rod bundle channel, and the flow and heat transfer in rod bundle channel and subchannel under rolling motion was discussed in detail. In addition, the interactive relationship between rolling motion and nuclear feedback were investigated, which demonstrated that the flow rate was reduced and heat transfer was enhanced in rod bundle under rolling motion, and the effects of rolling motion on subchannel were not the same. The average power was reduced and fluctuation of mass flow rate was inhibited in rod bundle under rolling motion when the nuclear feedback was considered.
- 【会议录名称】 第十四届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2015年度学术年会论文集
- 【会议名称】第十四届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2015年度学术年会
- 【会议时间】2015-09-23
- 【会议地点】中国北京
- 【分类号】TL33;TM623
- 【主办单位】中国核学会核能动力分会反应堆热工流体专业委员会