快堆核电蒸汽管道疏水系统的设计研究

Design Research on Steam Drain System of Fast Reactor Nuclear Power Plants

摘要:
目的快堆核电厂蒸汽参数有别于常规火电厂和压水堆核电厂，因此有必要对蒸汽管道的疏水系统设计进行研究。
方法结合常规火电厂和压水堆核电厂的设计经验，对蒸汽管道的疏水系统从系统配置和控制策略等方面进行梳理和研究。
结果基于上述分析的结果、并针对快堆蒸汽系统的特点，提出了适用于快堆核电厂疏水系统的优化设计方案。
结论研究结果显示优化设计方案满足了快堆核电厂的设计要求，同时本研究结果也可为后续其他核电厂提供参考。

Abstract:
Introduction The steam parameters of sodium-cooled fast reactor is different from PWR nuclear power or conventional fossil-fuel power plant， so it's necessary to restudy the drain system.
Method Specific to PWR nuclear power plant or conventional fossil-fuel power plant， the steam drain system was collated and discussed from aspects such as the components and control logic.
Result Then an optimized system is developed for fast reactor power unit based on the above analysis result and the characteristics of the steam system.
Conclusion The result shows that the optimized drain system can meet with the requirement of fast reactor power unit， and it also can be a reference for construction of future reactor units.