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Experimental study on natural circulation and gas injection enhanced circulation in KYLIN-II mixed circulation loop

  • L. V. Kefeng
  • , Sheng Gao
  • , Liuli Chen
  • , Chenchong Yue
  • , Mariano Tarantino
  • , Qunying Huang
  • , Yican Wu
  • Chinese Academy of Sciences
  • Jiangsu Higher Education Institutions
  • Agenzia nazionale per le nuove tecnologie, l'energia e lo sviluppo economico sostenibile

科研成果: 书/报告/会议事项章节会议稿件同行评审

摘要

Pure lead and its alloys are foreseen to be used as coolant and/or spallation target in the advanced nuclear systems. To investigate the behavior of Lead Bismuth Eutectic (LBE) cooled nuclear systems, KYLIN-II Thermal-Hydraulic (KYLIN-II TH) mixed circulation test loop has been designed and built in HEFEI by FDS team. The loop is a multipurpose facility aimed to investigate natural circulation, forced circulation and gas enhanced circulation in HLM systems. In this context, experimental data and correlations for the design of nuclear systems cooled with heavy liquid metals will be gained. The work concerns the preliminary tests performed on KYLIN-II TH. During the experiments, the facility was operated at 200-350 °C with heating power from 16 kW to 70 kW. The natural circulation, transient circulation and preliminary Loss of Flow Accident (LOFA) was carried out in this work. The experiments show that the steady state of natural circulation is easy to be established in a few minute. The time duration of temperature transition state, during the foundation of natural circulation in start-up of natural circulation test and LOFA in this work, is less than 300 s, however, depended on the operation parameters of the facility.

源语言英语
主期刊名International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
出版商American Nuclear Society
7426-7433
页数8
ISBN(电子版)9781510811843
出版状态已出版 - 2015
活动16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, 美国
期限: 30 8月 20154 9月 2015

出版系列

姓名International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
9

会议

会议16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
国家/地区美国
Chicago
时期30/08/154/09/15

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