快堆燃料组件管脚开孔孔径选型水力实验研究
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摘要
管脚位于快堆燃料组件入口处,其结构尺寸直接决定了进入燃料组件内部的冷却剂流量,对于燃料组件压力损失、流速分布等流体力学行为均有重要影响。目前关于燃料组件的相关研究多集中于棒束区热工流体力学特性,管脚段研究较为缺乏,且尚无明确的选型标准,故在工程实践之前,有必要进一步研究快堆燃料组件管脚的流体力学特性,完善选型标准,为结构设计提供参考。本文通过水力实验,研究了不同开孔孔径的燃料组件管脚对应阻力系数分布、流量与压降对应关系等流体力学性能。结果显示,管脚开孔孔径直接决定了冷却剂钠的质量流量与压降对应关系,可以通过改变管脚开孔孔径调节进入不同分区的燃料组件入口流量,使之具有大致相等的压降;本文引入了管脚收缩系数这一无量纲数,提出与管脚结构参数有关的阻力系数经验关系式,用于快堆燃料组件管脚阻力系数及压降的一般估算;基于设计要求的压降与开孔流速限值,本文给出了快堆燃料组件管脚开孔孔径选型推荐方案,供相关实验或工程参考。
The entry tube locates at the coolant inlet of the fast reactor fuel assembly,which directly determines the flow rate of the sodium coolant entering the interior of the fuel assembly to cool the fuel-rod bundles. It has important influence on the pressure drop and flow-velocity distribution of the fuel assembly. At present,the research on fast reactor fuel assembly is mostly focused on the thermal-hydraulic characteristics of the fuel-rod bundles,while there is lack of the research about the entry tube,especially there is no uniform design standard. Therefore,it is necessary to further study the flow characteristics about the entry tube of fast reactor fuel assembly to provide a reference for structure design. In this study,the distribution of resistance coefficient and the relationship between flow rate and pressure drop of entry tube with different diameter are studied by hydraulic experiment. The results show that the diameter of the entry-tube hole has the significant impact on the flow characteristics of sodium coolant,so the inlet flow rate of the fuel assembly in different core-region can be adjusted by changing the diameter of the entry-tube hole to achieve the balance of pressure drop of fuel assembly. In addition,a dimensionless contraction coefficient of the entry tube is introduced and the empirical correlations of the resistance coefficient are formulated which are used to estimate the pressure drop of the in fast reactor fuel assembly. Finally,based on the design requirements of pressure drop and flow-velocity limitation,a recommended program is presented of diameter selection about the entry-tube hole,which can be used as a reference for relevant experiments or engineering.
The entry tube locates at the coolant inlet of the fast reactor fuel assembly,which directly determines the flow rate of the sodium coolant entering the interior of the fuel assembly to cool the fuel-rod bundles. It has important influence on the pressure drop and flow-velocity distribution of the fuel assembly. At present,the research on fast reactor fuel assembly is mostly focused on the thermal-hydraulic characteristics of the fuel-rod bundles,while there is lack of the research about the entry tube,especially there is no uniform design standard. Therefore,it is necessary to further study the flow characteristics about the entry tube of fast reactor fuel assembly to provide a reference for structure design. In this study,the distribution of resistance coefficient and the relationship between flow rate and pressure drop of entry tube with different diameter are studied by hydraulic experiment. The results show that the diameter of the entry-tube hole has the significant impact on the flow characteristics of sodium coolant,so the inlet flow rate of the fuel assembly in different core-region can be adjusted by changing the diameter of the entry-tube hole to achieve the balance of pressure drop of fuel assembly. In addition,a dimensionless contraction coefficient of the entry tube is introduced and the empirical correlations of the resistance coefficient are formulated which are used to estimate the pressure drop of the in fast reactor fuel assembly. Finally,based on the design requirements of pressure drop and flow-velocity limitation,a recommended program is presented of diameter selection about the entry-tube hole,which can be used as a reference for relevant experiments or engineering.
引文
[1]徐铼.快堆核我国核能的可持续发展[J].中国核能可持续发展.
[2]李淞,周志伟,冯预恒.CEFR堆芯组件安装方式对组件件流量分配的影响[J].原子能科学技术,2015,49(2):207-211.
[3]李淞,齐少璞,马晓,等.CEFR流量1区燃料组件管脚流量分配数值模拟[J].原子能科学技术,2014,48(2):251-256.
[4]冯预恒,胡文军,乔学冬,等.CERFⅠ-Ⅱ型栅板联箱截流件的数值模拟ANSYS CFX流体分析及仿真[J].原子能科学技术,2008,42(增刊):150-154.
[5]程道喜,齐晓光,翟伟明,等.快堆转换区组件、含镎嬗变组件模拟机水力实验[J].重大核科学工程·中国实验快堆.
[6]刘洋,喻宏,周志伟.钠冷快堆燃料组件热工水力特性数值模拟与分析[J].原子能科学技术,2014,48(10):1790-1796.
[7]刘洋,喻宏.快堆燃料组件热工流体力学计算研究[J].原子能科学技术,2008,42(2):128-134.
[8]丁振鑫.快堆燃料组件水力特性计算[J].原子能科学技术,1991,25(5):25-29.
[9]Young-Kyu Lee,Jae-Han Lee.Drop performance test of conceptually designedcontrol rod assembly for prototype generation IV sodium-cooled fast reactor.Nuclear Engineering and Technology.49(2017)855-864.
[10]Seok-Kyu Chang,Dong-jin Euh.Flow distribution and pressure loss in subchannels of a wire-wrapped 37-pin rod bundle for a sodium-cooled fast reactor.Nuclear Engineering and Technology.48(2014)376-385.
[11]IAEA.Status of Fast Reactor Research and Technology Development.IAEA-TECDOC-1691(2012).International Atomic Energy Agency,Vienna.
[12]孔珑.工程流体力学(第四版)[M].北京:中国电力出版社,2014:116-117.
[13]杨世铭,陶文铨.传热学[M].北京:高等教育出版社,2012:237-243.
[14]赵兆颐,朱瑞安.反应堆热工流体力学[M].北京:清华大学出版社,1992:289-290.
[2]李淞,周志伟,冯预恒.CEFR堆芯组件安装方式对组件件流量分配的影响[J].原子能科学技术,2015,49(2):207-211.
[3]李淞,齐少璞,马晓,等.CEFR流量1区燃料组件管脚流量分配数值模拟[J].原子能科学技术,2014,48(2):251-256.
[4]冯预恒,胡文军,乔学冬,等.CERFⅠ-Ⅱ型栅板联箱截流件的数值模拟ANSYS CFX流体分析及仿真[J].原子能科学技术,2008,42(增刊):150-154.
[5]程道喜,齐晓光,翟伟明,等.快堆转换区组件、含镎嬗变组件模拟机水力实验[J].重大核科学工程·中国实验快堆.
[6]刘洋,喻宏,周志伟.钠冷快堆燃料组件热工水力特性数值模拟与分析[J].原子能科学技术,2014,48(10):1790-1796.
[7]刘洋,喻宏.快堆燃料组件热工流体力学计算研究[J].原子能科学技术,2008,42(2):128-134.
[8]丁振鑫.快堆燃料组件水力特性计算[J].原子能科学技术,1991,25(5):25-29.
[9]Young-Kyu Lee,Jae-Han Lee.Drop performance test of conceptually designedcontrol rod assembly for prototype generation IV sodium-cooled fast reactor.Nuclear Engineering and Technology.49(2017)855-864.
[10]Seok-Kyu Chang,Dong-jin Euh.Flow distribution and pressure loss in subchannels of a wire-wrapped 37-pin rod bundle for a sodium-cooled fast reactor.Nuclear Engineering and Technology.48(2014)376-385.
[11]IAEA.Status of Fast Reactor Research and Technology Development.IAEA-TECDOC-1691(2012).International Atomic Energy Agency,Vienna.
[12]孔珑.工程流体力学(第四版)[M].北京:中国电力出版社,2014:116-117.
[13]杨世铭,陶文铨.传热学[M].北京:高等教育出版社,2012:237-243.
[14]赵兆颐,朱瑞安.反应堆热工流体力学[M].北京:清华大学出版社,1992:289-290.