摘要
为论证大型非能动核电厂空气导流板优化方案的可行性,搭建了安全壳冷却能力验证试验台架(COCOVET)。本文选取COCOVET空气冷却试验工况,采用粒子图像测速(PIV)手段将非能动安全壳冷却系统(PCS)环腔的空气流动可视化,通过对比试验数据和程序模拟结果,研究PCS环腔空气强迫对流和自然对流并存的混合对流换热现象,论证导流板优化方案可行性。研究结果表明:PCS环腔下降段空气到达导流板尾部区域后,大部分空气折流180°进入上升段,沿导流板向上流动,少量空气沿冷却面继续向下流动。在无导流板区域,加热面传热方式以偏自然对流类型为主,加热面热流密度沿高度方向基本不变。在有导流板区域,PCS环腔上升段存在明显的入口效应,加热面热流密度呈现迅速增加后降低的趋势。安全壳安全分析程序计算值和试验值符合良好,适用于模拟空气混合对流换热过程。研究结果验证了大型非能动核电厂导流板优化方案可行性,也丰富了空气混合对流换热研究内容。
Containment cooling capability verification test(COCOVET)is conducted to confirm air baffle removal code for passive nuclear power plant.The shrink ratio of passive containment cooling system(PCS)air passage between the test body and the prototype is 1∶4.In the COCOVET air convection heat transfer test,the flow around and separation of air at the tail end of the baffle are observed within the operating parameters of the PCS system,and the test working condition matrix is determined within the parameter range to study the mixed convective heat transfer characteristics of air and the containment wall.COCOVET air cooling test conditions were selected in this paper,and particle image velocimetry(PIV)was used to visualize the air flow in the containment annulus.By comparing the test data and code simulation results,the mixed convection heat transfer phenomenon of forced and natural air convection coexisting in the containment annulus was studied,the applicability of the safety analysis code of the containment was verified,the response of the containment after the accident was simulated,the cooling capacity of the containment was evaluated,and the feasibility of the optimization scheme of the baffle was demonstrated.The research results show that after the air reaches the tail area of the air baffle,most of the air in the descending section of the containment annulus enters the rising section 180°and flows upward along the baffle,while a small amount of air continues to flow downward along the cooling surface.In the area without baffle,the heat transfer mode of heating surface is mainly natural convection type,and the heat flux of heating surface is basically unchanged along the height direction.In the area with baffle,there is an obvious inlet effect in the rising section of the containment annulus,and the heat flux on the heating surface increases rapidly and then decreases.By using the lumped parameter and three-dimensional parameter modeling method and the mixed convective heat transfer empirical equation,the ca
作者
杨鹏
王国栋
李万总
黄思洋
周明慧
刘宇
YANG Peng;WANG Guodong;LI Wanzong;HUANG Siyang;ZHOU Minghui;LIU Yu(Nuclear and Radiation Safety Center,Ministry of Ecology and Environment,Beijing 102401,China;Shanghai Nuclear Engineering Research&Design Institute,Shanghai 200233,China;Shanghai Nuclear Equipment Test Center,Shanghai 200233,China)
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2024年第4期771-782,共12页
Atomic Energy Science and Technology
