摘要
开展堆腔注水冷却系统的临界热流密度(CHF)实验。采用等宽矩形发热段模拟压力容器下封头,分别在池式沸腾及强迫循环工况条件下,对发热壁面不同角度位置处的CHF限值进行实验研究。实验结果表明:在池式沸腾和强迫循环工况条件下,CHF随角度的变化关系都可以分为3段,在靠近入口的区域,池式沸腾条件下CHF随角度增加而升高,而强迫循环工况条件下CHF随角度增加逐渐降低;在中部区域,CHF随角度增加而升高;在靠近出口的区域,CHF随角度增加而降低。
An experiment was conducted to study the critical heat flux in the cavity injection system. A constant-width slice heater block was used for the representing of the reactor vessel lower head, in combination with a power-shaping approach, in the experiment. The critical heat flux（CHF） at various angular position of the external wall was measured under the pool-boiling condition and the forced cooling condition, respectively. The experimental results indicated that, under both pool-boiling condition and forced cooling condition, the variation in CHF at different angular position can be divided into three kinds. In the inlet region, the critical heat flux increases with the increasing of the angular position under pool-boiling condition, but under forced cooling condition the critical heat flux decreases with the increasing of the angular position. In the middle region, the critical heat flux increases with the increasing of the angular position. In the outlet region, the critical heat flux decreases with the increasing of the angular position.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2016年第5期4-9,共6页
Nuclear Power Engineering
