不同运行参数对压力容器外部冷却临界热流密度影响实验研究

Experimental Study on Influence of External Pressure Vessel Cooling Parameters on Critical Heat Flux

  • 摘要: 国内外众多三代核电采用的是非能动冷却的熔融物滞留措施,华龙一号(HPR1000)为应对极端严重事故而设置了能动与非能动相结合的堆腔注水冷却系统。为了评估该系统的能动子系统的运行特性,采用等宽矩形结构发热体模拟了压力容器的下封头,在强迫驱动冷却条件下,实验研究了不同运行参数对临界热流密度的影响。实验结果表明:在靠近出口的区域,随着角度的增加,临界热流密度会发生降低。在中部区域,随着角度的增加,临界热流密度随之增加,在82.5°位置处形成局部峰值。在靠近入口的区域,当入口过冷度较高(约30 ℃)时,入口效应的影响较为显著,入口位置的临界热流密度高于中部区域的临界热流密度。高入口过冷度工况(约70 ℃)条件下,冷却流量的增加对临界热流密度的影响更为明显。低入口过冷度工况(约7 ℃)时,过冷度和压力的变化对临界热流密度的影响更为明显。

     

    Abstract: In-vessel retention (IVR) of molten material, as one of the most important mitigation measures for serious accidents, can effectively prevent the leakage of molten material from the core to the outside of the pressure vessel, resulting in the release of a large amount of radioactive material. Hua-long Pressurized Reactor (HPR1000) has set up a combined active and passive reactor cavity injection cooling (CIS) system to cope with similar extremely serious accidents. Under severe accident conditions, it implements external pressure vessel cooling to achieve the IVR of molten material. To ensure the success of the molten material retention strategy, it is necessary to maintain the heat flux on the outer wall of the pressure vessel lower head below the critical heat flux (CHF) under this operating condition during the implementation of external reactor vessels cooling. In order to evaluate the external pressure vessel cooling capacity limit of the active subsystem of the CIS system, a rectangular heating element with equal width was used to simulate the lower head of the pressure vessel. Under forced driving cooling conditions, the influences of different operating parameters such as inlet subcooling, cooling flow rate, and pressure on the critical heat flux were experimentally studied. The gap spacing size, outlet pressure, inlet subcooling and other conditions of the sealed flow channel of the experimental simulation are consistent with the external cooling process of the lower head of the CIS system of HPR1000. In addition, the wall heat flux and coolant flow rate of the CIS system were also accurately simulated by means of a specific modeling method. A discrete plurality of electric heating elements was used as heat sources, and the power of each group of electric heating elements was controlled independently in groups to achieve the desired heat flux distribution. The experimental results indicate that, under the conditions of 0.1 MPa at the outlet pressure of the pipeline and 400 t/h and 860 t/h coolant flow rate of the CIS system, the critical heat flux decreases with the increase of angle in the area near the outlet. In the central region, the critical heat flux also increases with the angle. The experimental results also indicate that, in the area near the inlet, the critical heat flux decreases with the increase of angle, and the effect of the inlet effect is more significant when the subcooling at the inlet is high.

     

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