Dynamic Response of Hot/Cold Liquid Interfaces to Pump Speed Perturbations in a Thermal-Hydraulic Loop Simulating a PIUS-type Reactor.

DOI Web Site 被引用文献2件 参考文献8件
  • SIBAMOTO Yasuteru
    Department of Nuclear Safety Research, Japan Atomic Energy Research Institute
  • YONOMOTO Taisuke
    Department of Nuclear Safety Research, Japan Atomic Energy Research Institute
  • KUKITA Yutaka
    Department of Nuclear Safety Research, Japan Atomic Energy Research Institute
  • TSUJI Yoshiyuki
    Department of Energy Engineering and Science,Nagoya University
  • TAMAKI Masayoshi
    Department of Energy Engineering and Science,Nagoya University

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  • Dynamic Response of Hot Cold Liquid Int

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The operation of a PIUS-type reactor requires controlling the reactor pump speed to keep stationary the hot/cold liquid interfaces between the reactor coolant and cold borated water. The dynamic response of the interface location to pump speed perturbations is analyzed for an experimental loop simulating a PIUS-type reactor. The transfer function between the pump speed and the interface location is obtained by perturbing and Laplace-transforming the one-dimensional fluid momentum equations. The analytical results agree well with experimental data taken from the same facility. It is shown that the magnitude of the phase lag in the response of the interface location, which needs to be considered in designing a pump speed controller, primarily depends on the fluid inertia in the loop, the density lock flow area, and the density difference between the simulated reactor coolant and borated water.

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