首页> 中文期刊> 《热力发电》 >百万千瓦级核电机组直接空冷排汽管道水力特性数值模拟

百万千瓦级核电机组直接空冷排汽管道水力特性数值模拟

         

摘要

水资源匮乏制约我国发展内陆核电,借鉴火电机组,采用直接空冷是最好的选择.为了保证其排汽管道设计的合理性,结合目前我国百万千瓦级核电机组堆型特点,提出了2种可用于不同堆型的直接空冷排汽管道型式,并采用计算流体动力学(CFD)模拟方法对其水力特性进行了分析.结果表明:管系流量分配以上部T型三通为中心两侧成对称分布,中间2支管分配的流量最多;各支管流量分配均匀,流量偏差控制在5%左右;各工况下排汽管道系统压降随机组背压变化明显,背压越低压降越大;在相同背压工况下,管系总压降随蒸汽流量增大而增大,系统总压降排序为EPR1000(四排汽)>AP1000>EPR1000(六排汽)>CPR1000.该结果可为后续工程的可行性研究提供技术支撑.%According to the characteristics of reactor types for present 1000 MW level nuclear power units in China, two types of exhaust pipe for direct air cooling system applied for different reactor types were put forward. Focusing on the steam flow distribution and flow resistance problem, the hydraulic characteristics for the two different pipe layouts were simulated by using the computational fluid dynamics (CFD) method. The results show that, the branches flow symmetrically distributes about the upper central tee joint, with the maximum flow at the two branches in the middle. The flow distribution of each branch is uniform, and the flow deviation is controlled at about 5%. The system flow resistance is strongly related to the back pressure, the lower the back pressure, the greater the system flow resistance. The system flow resistance increases with the steam flow under the same back pressure condition, the order of the system flow resistance value was: EPR1000 (quadruple-flow)>AP1000> EPR1000(sextuple-flow )>CPR1000. The results can provide technical support for further engineering practice.

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