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作 者:王心安 张大林[2] 王婷 秋穗正[2] 苏光辉[2] Wang Xinan;Zhang Dalin;Wang Ting;Qiu Suizheng;Su Guanghui(China Nuclear Power Technology Research Institute Co.,Ltd.,Shenzhen,Guangdong,518000,China;State Key Laboratory of Multiphase Flow in Power Engineering,Xi’an Jiaotong University,Xi’an,710049,China)
机构地区:[1]中广核研究院有限公司,广东深圳518000 [2]西安交通大学动力工程多相流国家重点实验室,西安710049
出 处:《核动力工程》2024年第2期147-153,共7页Nuclear Power Engineering
摘 要:为准确预测钠冷快堆堆芯三维热工水力参数分布同时降低计算资源需求,基于表征体元概念建立了针对绕丝棒束组件的三维多孔介质模型,根据组件几何结构特点将冷却剂与固体壁面间的相互作用力分解为分布式阻力,引入包含湍流搅混传热、流体导热和燃料棒导热的有效传热系数模型刻画组件的径向传热。采用日本东芝公司核能工程实验室37棒液态钠冷却绕丝棒束组件实验进行模拟计算,数值计算结果与实验结果对比发现,基于论文提出的多孔介质模型可以在多种工况下较好地复现实验结果。因此,本研究提出的多孔介质模型可用于钠冷快堆绕丝棒束组件三维热工水力参数分布预测。In order to accurately predict the distribution of three-dimensional thermal-hydraulic parameters in the core of sodium-cooled fast reactor and reduce the demand for computing resources,a three-dimensional porous medium model for the wire-wrapped fuel assembly was established based on the concept of representative element volume.The interaction between the coolant and the solid surface is decomposed into distributed resistance force according to the geometry characteristics of the assembly.An effective heat transfer coefficient model including turbulent mixing heat transfer,fluid heat transfer and fuel rod heat transfer was introduced to describe the radial heat transfer of the assembly.Numerical analysis was performed for the liquid sodium cooled 37-pin wire wrapped fuel assembly experiment conducted by the Nuclear Energy Engineering Laboratory of Toshiba Corporation.Compared with the experimental results,the numerical calculation results show that the porous medium model proposed in this paper can well reproduce the experimental results under various conditions.Therefore,the porous medium model proposed in this study can be used to predict the distribution of three-dimensional thermal-hydraulic parameters of the wire-wrapped fuel assembly of sodium-cooled fast reactor.
关 键 词:钠冷快堆 绕丝棒束组件 表征体元概念 多孔介质模型
分 类 号:TL334[核科学技术—核技术及应用]
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