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清华大学学报(自然科学版)  2021, Vol. 61 Issue (4): 329-337    DOI: 10.16511/j.cnki.qhdxxb.2021.25.029
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高温气冷堆示范工程螺旋管式直流蒸汽发生器工程验证试验
李晓伟, 吴莘馨, 张作义, 赵加清, 雒晓卫
清华大学 核能与新能源技术研究院, 先进核能技术协同创新中心, 先进反应堆工程与安全教育部重点实验室, 北京 100084
Engineering test of HTR-PM helical tube once through steam generator
LI Xiaowei, WU Xinxin, ZHANG Zuoyi, ZHAO Jiaqing, LUO Xiaowei
Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Collaborative Innovation Center for Advanced Nuclear Energy Technology, Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China
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摘要 研发一种新型蒸汽发生器必须进行一定规模的工程验证试验。清华大学核能与新能源技术研究院在其实验基地建设了高温气冷堆示范工程(HTR-PM)螺旋管式直流蒸汽发生器的工程验证试验回路(engineering test facility for steam generator,ETF-SG)。工程验证试验回路能够模拟HTR-PM运行参数,可对HTR-PM蒸汽发生器一个换热组件进行1∶1的工程验证试验。回路设计热功率10 MW,氦回路设计压力8 MPa,最高设计温度800℃,二回路设计压力18 MPa,最高设计温度600℃。在工程验证试验回路上针对高温气冷堆蒸汽发生器完成了几十项热工水力试验,对蒸汽发生器的温度均匀性、堵管后温度分布及其温度展平调节、热工水力瞬态特性、两相流不稳定性等进行了试验研究,验证了HTR-PM螺旋管式直流蒸汽发生器的热工水力和结构设计,并为其调试、运行、低功率及启停工况参数的确定提供了重要数据和参考。
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李晓伟
吴莘馨
张作义
赵加清
雒晓卫
关键词 高温气冷堆(HTGR)蒸汽发生器工程验证试验两相流不稳定性温度均匀性    
Abstract:Scale engineering tests are necessary when developing a steam generator. An engineering test facility for the steam generator (ETF-SG) was built for HTR-PM at the Institute of Nuclear and New Energy Technology (INET), Tsinghua University. ETF-SG can simulate the HTR-PM steam generator operating parameters for full scale tests of one helical tube assembly. The design thermal power is 10 MW. The design temperature and pressure of the primary helium loop are 800℃ and 8 MPa. The design temperature and pressure of the secondary loop are 600℃ and 18 MPa. Thus, ETF-SG can be used for full scale engineering tests of the test steam generator. More than twenty thermal hydraulic experiments have been finished. The tests experimentally investigated the temperature uniformity, transient thermal hydraulic response, temperature uniformity after tube plugging and adjustments, two phase flow instability and other conditions. The tests verified the thermal hydraulic and structural designs of the HTR-PM steam generator. These experiments provide important data for the commissioning and operation of the HTR-PM nuclear power plant.
Key wordshigh temperature gas-cooled reactor (HTGR)    steam generator    engineering test    two phase flow instability    temperature uniformity
收稿日期: 2021-02-09      出版日期: 2021-04-16
基金资助:李晓伟,副教授,E-mail:lixiaowei@tsinghua.edu.cn;吴莘馨,教授,E-mail:xinxin@tsinghua.edu.cn;张作义,教授,E-mail:zyzhang@tsinghua.edu.cn
引用本文:   
李晓伟, 吴莘馨, 张作义, 赵加清, 雒晓卫. 高温气冷堆示范工程螺旋管式直流蒸汽发生器工程验证试验[J]. 清华大学学报(自然科学版), 2021, 61(4): 329-337.
LI Xiaowei, WU Xinxin, ZHANG Zuoyi, ZHAO Jiaqing, LUO Xiaowei. Engineering test of HTR-PM helical tube once through steam generator. Journal of Tsinghua University(Science and Technology), 2021, 61(4): 329-337.
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http://jst.tsinghuajournals.com/CN/10.16511/j.cnki.qhdxxb.2021.25.029  或          http://jst.tsinghuajournals.com/CN/Y2021/V61/I4/329
  
  
  
  
  
  
  
  
  
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