论文成果

发布时间：

2025-04-30

论文名称：

Subcooled flow boiling heat transfer of water in a circular tube under high heat fluxes and high mass fluxes.

发表刊物：

Fusion Engineering and Design

摘要：

Subcooled flow boiling under high heat flux and high mass flux (HHHM) conditions is commonly encountered in nuclear power engineering, for example, the heat removal technology for divertors in the International Thermonuclear Experimental Reactor (ITER). In the present study, subcooled flow boiling heat transfer of water was carried out experimentally in a uniformly heated vertical circular tube
with an inner diameter of 9.0 mm under HHHM conditions. Heat transfer coefficients were presented from single-phase convection to fully developed nucleate boiling. The effects of parameters, including mass flux (G = 6000, 8000, and 10,000 kg/m2 s), heat flux (q = 5–12.5 MW/m2), system pressure (P = 3, 4.2, and 5 MPa), and thermodynamic vapor quality (xth = −0.5 to −0.03), were discussed. Many previous heat transfer correlations available in the literature were assessed against our experimental data. Most of these correlations cannot predict the experimental data very well. A modified Chen correlation was developed, which predicted the total heat transfer coefficients with a mean average error of 1.11% and a root-meansquare error of 6.45%. A modified Lahey model was proposed to determine the contribution of nucleate boiling in the total heat transfer coefficient under HHHM conditions.

合写作者：

Jianguo Yan, Qincheng Bi, Zhaohui Liu∗, Ge Zhu, Laizhong Cai.

卷号：

100

页面范围：

406-418

是否译文：

否

发表时间：

2015-07-02