Local void measurements in integral-type experiments simulating nuclear power plant transients


Local void measurements in integral-type experiments simulating nuclear power plant transients

Ezsöl, G.; Szabados, L.; Prasser, H.-M.

The Paks Nuclear Power Plant is equipped with VVER-440/V213-type pressurised water reactors. As known, these reactors have a number of special features, therefore the transient behaviour should be different from PWRs of usual design.
To study the transient behaviour of this type of NPPs an integral-type facility called PMK-2, a scaled-down model of the Paks NPP was designed and constructed in the middle of 1980s and several experiments of different types have been performed.
In the framework of a European Union financed Phare project an upgrading of PMK-2 was performed. Equipments installed are as follows: needle-shaped void-probes for local void measurements, full-flow turbines for velocity measurements, micro-turbines for two-phase flow measurements, three beam gamma densitometer to measure coolant density and to identify flow patterns, and in addition a new data acquisition system has been installed.
This paper deals with the application of void probes for the evaluation of the results of a loss of coolant accident.

Keywords: Nuclear reactor safety; thermal hydraulics; integral test facilities; small break loca; void fraction measurement

  • Lecture (Conference)
    5th World Conference on Experimental Heat Transfer, Fluid Mechanics and Thermodynamics, Thessalonoki, Greece, 24-28 September 2001, Vol. 2, pp. 1637 - 1641.
  • Contribution to proceedings
    5th World Conference on Experimental Heat Transfer, Fluid Mechanics and Thermodynamics, Thessalonoki, Greece, 24-28 September 2001, Vol. 2, pp. 1637 - 1641.

Permalink: https://www.hzdr.de/publications/Publ-3854
Publ.-Id: 3854