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

[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 sys...

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Bibliographic Details
Main Authors: LIN Yan, YANG Daohong, SHI Haiyun
Format: Article
Language:English
Published: Energy Observer Magazine Co., Ltd. 2021-09-01
Series:南方能源建设
Subjects:
Online Access:https://www.energychina.press/en/article/doi/10.16516/j.gedi.issn2095-8676.2021.03.012
Description
Summary:[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.
ISSN:2095-8676