論文

2018年11月

MHD pressure drop measurement of PbLi flow in double-bended pipe

Fusion Engineering and Design
  • Shoki Nakamura
  • ,
  • Tomoaki Kunugi
  • ,
  • Takehiko Yokomine
  • ,
  • Zensaku Kawara
  • ,
  • Koji Kusumi
  • ,
  • Akio Sagara
  • ,
  • Juro Yagi
  • ,
  • Teruya Tanaka

136
開始ページ
17
終了ページ
23
記述言語
英語
掲載種別
研究論文(学術雑誌)
DOI
10.1016/j.fusengdes.2017.12.009
出版者・発行元
Elsevier {BV}

The design of liquid metal cooling system for the liquid blanket concepts in magnetic fusion reactor requires the magnetohydrodynamics (MHD) friction loss coefficients for various pipes including pipes and bents to estimate the pressure drop of the whole blanket. The aim of this study is to reveal the MHD pressure drop of PbLi flow in a double-bended pipe. The experiments were conducted in the Oroshhi-2 loop having a super conducting magnet of 3T at NIFS in Japan. In this paper, the MHD pressure drops of the pipe under the magnetic field of 0.5T-3.0T, the ranges of Reynolds number (Re) of 2000-200,000 and Hartmann number (Ha) of 106-640 at the upstream, double-bended and downstream regions were measured. As the results, all the MHD friction loss coefficients in three regions were well correlated with the interaction parameter (Na = Ha(2)/Re) in the range of 0.1 < N < 100. Finally, the correlation equations of MHD friction loss coefficient against the interaction parameters at the upstream, double-bended and downstream regions of the pipe were obtained. Moreover, it was briefly discussed on the implementation to the liquid metal cooling system design for fusion reactor.

リンク情報
DOI
https://doi.org/10.1016/j.fusengdes.2017.12.009
Web of Science
https://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcAuth=JSTA_CEL&SrcApp=J_Gate_JST&DestLinkType=FullRecord&KeyUT=WOS:000452583700005&DestApp=WOS_CPL
ID情報
  • DOI : 10.1016/j.fusengdes.2017.12.009
  • ISSN : 0920-3796
  • eISSN : 1873-7196
  • ORCIDのPut Code : 96316189
  • Web of Science ID : WOS:000452583700005

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