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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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
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spelling doaj-06cee66ba7704a4a916e33cd3d13d8cc2021-09-30T10:06:44ZengEnergy Observer Magazine Co., Ltd.南方能源建设2095-86762021-09-0183848810.16516/j.gedi.issn2095-8676.2021.03.012Design Research on Steam Drain System of Fast Reactor Nuclear Power PlantsLIN Yan0YANG Daohong1SHI Haiyun2China Energy Engineering Group Guangdong Electric Power Design Institute Co., Ltd., Guangzhou 510663, ChinaChina Energy Engineering Group Guangdong Electric Power Design Institute Co., Ltd., Guangzhou 510663, ChinaChina Energy Engineering Group Guangdong Electric Power Design Institute Co., Ltd., Guangzhou 510663, China[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.https://www.energychina.press/en/article/doi/10.16516/j.gedi.issn2095-8676.2021.03.012fast reactornuclear power plantsteam systemdrain systemfourth generation
collection DOAJ
language English
format Article
sources DOAJ
author LIN Yan
YANG Daohong
SHI Haiyun
spellingShingle LIN Yan
YANG Daohong
SHI Haiyun
Design Research on Steam Drain System of Fast Reactor Nuclear Power Plants
南方能源建设
fast reactor
nuclear power plant
steam system
drain system
fourth generation
author_facet LIN Yan
YANG Daohong
SHI Haiyun
author_sort LIN Yan
title Design Research on Steam Drain System of Fast Reactor Nuclear Power Plants
title_short Design Research on Steam Drain System of Fast Reactor Nuclear Power Plants
title_full Design Research on Steam Drain System of Fast Reactor Nuclear Power Plants
title_fullStr Design Research on Steam Drain System of Fast Reactor Nuclear Power Plants
title_full_unstemmed Design Research on Steam Drain System of Fast Reactor Nuclear Power Plants
title_sort design research on steam drain system of fast reactor nuclear power plants
publisher Energy Observer Magazine Co., Ltd.
series 南方能源建设
issn 2095-8676
publishDate 2021-09-01
description [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.
topic fast reactor
nuclear power plant
steam system
drain system
fourth generation
url https://www.energychina.press/en/article/doi/10.16516/j.gedi.issn2095-8676.2021.03.012
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AT yangdaohong designresearchonsteamdrainsystemoffastreactornuclearpowerplants
AT shihaiyun designresearchonsteamdrainsystemoffastreactornuclearpowerplants
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