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针对超临界水冷堆(SCWR)堆芯垂直上升类三角形子通道,开展超临界水的流动传热试验研究。反应堆堆芯类三角形子通道棒束直径为8 mm、栅距比为1.4。试验参数范围为:热流密度q=200~800 kW/m~2、压力P=23~28 MPa、质量流速G=700~1 300 kg/(m~2×s)。分析了q、P和G等热工参数对超临界水传热特性的影响。试验结果表明:超临界压力下,壁面温度T_w随q和P的增加而升高,传热系数峰值降低;提高G能够强化超临界水的传热,G增加,T_w降低,传热系数增大;当G增大到一定的程度,改变G对传热起到强化作用的效果不如在低G下显著;当q达到800 kW/m~2时,在大比热区,T_w随焓值变化剧烈,传热系数峰值不明显;当P提高到28 MPa时,大比热区的强化传热作用被削弱。
Aiming at the vertically rising triangular subcircuit of supercritical water cooled reactor (SCWR) core, the flow and heat transfer experiment of supercritical water was carried out. The reactor core triangular sub-channel bundles have a diameter of 8 mm and a pitch ratio of 1.4. The test parameters were as follows: heat flux q = 200-800 kW / m 2, pressure P = 23-28 MPa and mass flow rate G = 700-1 300 kg / (m 2 × s). The effects of thermal parameters such as q, P and G on the heat transfer characteristics of supercritical water were analyzed. The experimental results show that under supercritical pressure, the wall temperature T_w increases with the increase of q and P, and the peak value of heat transfer coefficient decreases. Increasing G can enhance the heat transfer of supercritical water, increasing G, decreasing T_w and increasing the heat transfer coefficient ; When G increases to a certain extent, the effect of changing G on heat transfer enhancement is not as remarkable as at low G; when q reaches 800 kW / m ~ 2, the variation of T_w with enthalpy Violently, and the peak value of heat transfer coefficient is not obvious. When P is increased to 28 MPa, the enhanced heat transfer in large heat zone is weakened.