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作 者:傅俊森 肖瑶[1] 陈硕 张伟 丛腾龙 顾汉洋[1] Fu Junsen;Xiao Yao;Chen Shuo;Zhang Wei;Cong Tenglong;Gu Hanyang(School of Nuclear Science and Technology,Shanghai Jiao Tong University,Shanghai,200240,China)
机构地区:[1]上海交通大学核科学与工程学院,上海200240
出 处:《核动力工程》2024年第3期132-138,共7页Nuclear Power Engineering
基 金:国家自然科学基金(12135008,12322510,12075150);上海启明星项目(22QA1404500)。
摘 要:燃料组件是反应堆的重要组成部件,临界热流密度是决定燃料组件性能的最关键参数之一。参考上海交通大学热工水力实验室的螺旋十字燃料元件参数,设计了19棒束螺旋十字燃料组件并开展临界热流密度特性实验研究,建立了一套适用于均匀发热全长螺旋燃料组件棒束临界热流密度测量方法,获得了螺旋燃料组件临界热流密度数据库,并对实验结果进行了分析。结果表明:临界功率随入口温度升高而线性降低,随着压力和干度的增大而减小,随质量流速的增大而增大。引入周向不均匀因子,建立了螺旋燃料临界热流密度预测模型,实验值(M)/预测值(P)数据的统计分布呈现正态分布,且均匀分布在1附近,证明了关系式的可靠性和准确性。所用实验技术和模型开发方法具有通用性,可应用于同类螺旋燃料组件临界热流密度特性研究。The fuel assembly is an important component of the reactor,and the critical heat flux(CHF)is one of the most critical parameters that determine the performance of the fuel assembly.With reference to the parameters of helical cruciform fuel elements in the Nuclear Engineering Thermal-Hydraulic Laboratory of Shanghai Jiao Tong University,a 19-pin helical cruciform fuel assembly was designed and the CHF experiment was carried out.A measurement method for the CHF of uniformly heated full-length helical fuel rod bundle was developed.The CHF database of helical fuel assemblies was obtained,and the experimental results were analyzed.The results show that the critical power decreases linearly with the increase of inlet temperature,pressure and dryness,and increases with the increase of mass flow rate.A CHF prediction model for helical fuel assembly is established by introducing a circumferential non-uniform factor.The statistical distribution of experimental value(M)/predicted value(P)data presents normal distribution and is uniformly distributed around 1,which proves the reliability and accuracy of the relationship.The proposed experimental technique and model development method are universal,and can be applied to the study of CHF characteristics of similar helical fuel assemblies.
关 键 词:燃料组件 螺旋十字燃料 临界热流密度 周向不均匀因子
分 类 号:TL334[核科学技术—核技术及应用]
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