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: | , , |
---|---|
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 |
id |
doaj-06cee66ba7704a4a916e33cd3d13d8cc |
---|---|
record_format |
Article |
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 |
work_keys_str_mv |
AT linyan designresearchonsteamdrainsystemoffastreactornuclearpowerplants AT yangdaohong designresearchonsteamdrainsystemoffastreactornuclearpowerplants AT shihaiyun designresearchonsteamdrainsystemoffastreactornuclearpowerplants |
_version_ |
1716863218187501568 |