摘要
以预测脉动流动下临界热流密度下降阈值的温度反馈模型为基础,用实验数据对理论预测结果进行修正,并根据修正后的临界热流密度下降阈值拟合了一个流量脉动条件下竖直小管径圆管内临界热流密度的半理论半经验预测公式。该公式预测值与低压低质量流速下Umekawa和Ozawa的脉动流动临界热流密度实验结果相比较,平均相对误差为11.15%,低于Kim关系式21.04%的预测误差。
The reduction limit of critical heat flux(CHF) in vertical tube under flow oscillation condition,obtained by a temperature response model,was modified using the CHF experimental data of Umekawa and Ozawa et al..Based on the modified reduction limit of CHF,a new correlation was proposed to predict the CHF under flow oscillation condition in vertical tubes at low velocity and pressure conditions.The comparisons between the prediction of the new correlation and experimental data show a reasonable agreement with a mean error of 11.5%,which is smaller than the error of prediction using Kim correlation,21.04%.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2010年第3期36-39,共4页
Nuclear Power Engineering
基金
国家自然科学基金项目(10675096)