| 快堆核电蒸汽管道疏水系统的设计研究 |
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| 引用本文： | 林燕,杨道宏,施海云. 快堆核电蒸汽管道疏水系统的设计研究[J]. 南方能源建设, 2021, 8(3): 84-88. DOI: 10.16516/j.gedi.issn2095-8676.2021.03.012 |
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| 作者姓名： | 林燕 杨道宏 施海云 |
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| 作者单位： | 中国能源建设集团广东省电力设计研究院有限公司,广州510663 |
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| 基金项目： | 中国能建广东院科技项目“四代核电和小型反应堆核电设计关键技术研究”EV04101W |
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| 摘 要： | [目的]快堆核电厂蒸汽参数有别于常规火电厂和压水堆核电厂,因此有必要对蒸汽管道的疏水系统设计进行研究.[方法]结合常规火电厂和压水堆核电厂的设计经验,对蒸汽管道的疏水系统从系统配置和控制策略等方面进行梳理和研究.[结果]基于上述分析的结果、并针对快堆蒸汽系统的特点,提出了适用于快堆核电厂疏水系统的优化设计方案.[结论]...
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| 关 键 词： | 快堆 核电厂 蒸汽 疏水 四代 |
| 收稿时间： | 2020-12-01 |
Design Research on Steam Drain System of Fast Reactor Nuclear Power Plants |
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| Affiliation: | China Energy Engineering Group Guangdong Electric Power Design Institute Co.， Ltd.， Guangzhou510663， China |
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| Abstract: | 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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