摘要
在AP1000机组中,安全壳内滤网设备用于过滤失水事故后循环冷却水中的杂质,确保非能动堆芯冷却系统(PXS)正常运行。压损是滤网设备重要性能指标,滤网设备压损不能超过规定限值,以保证事故后有足够的循环冷却水可以冷却堆芯。滤网设备压损分为过滤部分压损和流道部分压损,文中通过试验手段和模拟计算的方法分别得出了一种新型滤网设备的各部分压损值。研究结果表明,在电厂极限工况条件下,该新型滤网设备过滤部分最大压损为0.329kPa,流道部分最大压损为0.636kPa,总压损为0.965kPa,远远小于1.72kPa的设计要求值。本研究结果为此种新型滤网设备下一步投入实际使用奠定了坚实基础。
In the AP1000 nuclear power plant,the design function for the In Containment Refueling Water Storage Tank（IRWST）and Containment Recirculation（CR）Screens is to prevent debris from being injected into the Reactor Coolant System during passive core cooling operations.Each screen must allow the recirculation of reactor coolant flow through while minimizing head loss and maintaining the required design flow rate.Screens head loss can be divided into filter section head loss and flow channel head loss.An experiment apparatus which can measure the filter section head loss is introduced.The flow channel head loss is studied by numerical calculation method which is also given a detailed description.The results show that,in limiting case,the filter section head loss is 0.329 kPa,the flow channel head loss is 0.636 kPa,the total head loss,or say screens head loss,is 0.965 kPa,which is far lower than design requirement 1.72 kPa.The study lays a foundation for the screens to put into use.
出处
《核科学与工程》
CSCD
北大核心
2017年第3期367-373,共7页
Nuclear Science and Engineering
基金
国家能源应用技术研究及工程示范项目(NY20140203)
关键词
滤网
AP1000
核电站
数值计算
Screen
AP1000
Nuclear Power Plant
Numerical Calculation
