Research on enhancement of natural circulation capability in lead-bismuth alloy cooled reactor by using gas-lift pump

Juanli Zuo, Wenxi Tian, Ronghua Chen, Suizheng Qiu, Guanghui Su

研究成果: Article

10 引用 (Scopus)

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The gas-lift pump has been adopted to enhance the natural circulation capability in the type of lead-bismuth alloy cooled reactors such as Accelerator Driven System (ADS) and Liquid-metal Fast Reactor (LMFR). The natural circulation ability and the system safety are obviously influenced by the two phase flow characteristics of liquid metal-inert gas. In this study, LENAC (LEad bismuth alloy NAtural Circulation capability) code has been developed to evaluate the natural circulation capability of lead-bismuth cooled ADS with gas-lift pump. The drift flow theory, void fraction prediction model and friction pressure drop prediction model have been incorporated into LENAC code. The calculation results by LENAC code show good agreement with experiment results of CIRCulation Experiment (CIRCE) facility. The effects of the gas mass flow rate, void fraction, gas quality, bubble diameter and the rising pipe height or the potential difference between heat exchanger and reactor core on natural circulation capability of gas-lift pump have been analyzed. The results showed that in bubbly flow pattern, for a fixed value of gas mass flow rate, the natural circulation capability increased with the decrease of the bubble diameter. In the bubbly flow, slug flow, churn flow and annular flow pattern, with the gas mass flow rate increasing, the natural circulation capability initially increased and then declined. And the flow parameters influenced the thermal hydraulic characteristics of the reactor core significantly. The present work is helpful for revealing the law of enhancing the natural circulation capability by gas-lift pump, and providing theoretical basis of the optimization design of cooling and system safety.

元の言語English
ページ(範囲)1-9
ページ数9
ジャーナルNuclear Engineering and Design
263
DOI
出版物ステータスPublished - 2013

    フィンガープリント

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Mechanical Engineering
  • Safety, Risk, Reliability and Quality
  • Materials Science(all)
  • Nuclear and High Energy Physics
  • Waste Management and Disposal

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