期刊文献+

竖直圆管内脉动流量下临界热流密度预测

Prediction of Critical Heat Flux in Vertical Tube under Flow Oscillation Condition
下载PDF
导出
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)
关键词 脉动流量 临界热流密度 临界热流密度下降阈值 温度反馈模型 Oscillation fluid Critical heat flux Reduction limit of CHF Temperature response model
  • 相关文献

参考文献5

  • 1Mamoru Ozawa, Hisashi Umekawa, Yohji Yoshika, et al. Dryout under Oscillatory flow Condition in Vertical and Horizontal Tubes--Experiments at Low Velocity and Pressure Conditions [J]. International Journal of Heat and Mass Transfer, 1993, 36 (16): 4076-4078.
  • 2Mamoru Ozawa, Hisashi Umekawa, Kaichiro Mishima, et al. CHF in Oscillatory Flow Boiling Channels [J]. Chemical Engineering Research and Design, 2001, 79(4): 389-401.
  • 3Umekawa H, Ozawa M, Miyazaki A. CHF in a Boiling Channel under Oscillatory Flow Condition [C]. Proceedings of the Second International Conference on Multiphase Flow, Kyoto, Japan, 1995.
  • 4Umekawa Hisashi, Ozawa Mamoru, Mitsunaga Tamotsu, et al. Scaling Parameter of CHF under Oscillatory Flow Conditions [J]. Heat Transfer-Asian Research,1999, 28(6): 541-550.
  • 5Yun Il Kim, Won-Pil Baek, Soon Heung Chang. Critical Heat Flux under Flow Oscillation of Water at Low- Pressure, Low-Flow Conditions [J]. Nuclear Engineering and Design 1999, 193 (1-2): 131-143,.

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部