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...
Main Authors: | , , |
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Format: | Article |
Language: | English |
Published: |
Energy Observer Magazine Co., Ltd.
2021-09-01
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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 |
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. |
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ISSN: | 2095-8676 |