<trans-title>Design Research on Steam Drain System of Fast Reactor Nuclear Power Plants

Yan LIN; Daohong YANG; Haiyun SHI

doi:10.16516/j.gedi.issn2095-8676.2021.03.012

LIN Yan,YANG Daohong,SHI Haiyun.Design Research on Steam Drain System of Fast Reactor Nuclear Power Plants[J].Southern Energy Construction,2021,08(03):84-88.. DOI: 10.16516/j.gedi.issn2095-8676.2021.03.012

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

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

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