原子能科学技术2018，Vol.52Issue(5)：816-821,6.DOI:10.7538/yzk.2018.52.05.0816
竖直圆管内向上流动的干涸实验研究
Experimental Investigation on Dryout in Upflow Vertical Tube
杨兵 1赵民富 1陈玉宙 1毕可明 1张东旭 1杜开文1
作者信息
- 1. 中国原子能科学研究院 反应堆工程技术研究部,北京102413
- 折叠
摘要
Abstract
The critical heat flux (CHF) experiment was performed in a tube with inner diameter of 8.2 mm and heated length of 2.4 m.The pressure is 3.2-19.7 MPa,mass flux is 963-2 707 kg/(m2 · s),inlet subcooling is 34-213 ℃ and outlet quality is 0.11-0.78.The results show that the CHF almost goes up linearly while mass flux or inlet subcooling increases,and falls down rapidly while the outlet quality rises.Based on the two-phase parameter analysis,it is found that within the experiment parameter range,the CHF is much related to vapor velocity.Criticality occurs when the liquid near the wall vanishes due to vapor entrainment after reaching the critical vapor velocity.As a result,the surface tension decreases with the increase of the pressure,the liquid film tends to tear out and the critical vapor velocity falls down while pressure rises.Based on the critical vapor velocity Ucr from experimental data of high pressure and the initiation entrainment velocity U0 proposed by Steen and Wallis,a prediction model for the critical vapor velocity was presented.The predicted results by this model agree well with the experimental data of low pressure.关键词
临界热流密度/干涸/反应堆安全Key words
critical heat flux/dryout/reactor safety分类
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杨兵,赵民富,陈玉宙,毕可明,张东旭,杜开文..竖直圆管内向上流动的干涸实验研究[J].原子能科学技术,2018,52(5):816-821,6.
