Experimental investigations of single and two-phase flow in a heated rod bundle

Author:

Barthel F.12,Franz R.32,Hampel U.45

Affiliation:

1. Frank Barthel, E-mail:

2. Helmholtz-Zentrum Dresden-Rossendorf, Institut für Fluiddynamik, Bautzner Landstraße 400, 01328 Dresden

3. Ronald Franz, E-mail:

4. Prof. Dr. Uwe Hampel, E-mail: , Helmholtz-Zentrum Dresden-Rossendorf, Institut für Fluiddynamik, Bautzner Landstraße 400, 01328 Dresden

5. AREVA-Stiftungsprofessur für Bildgebende Messverfahren für die Energie- und Verfahrenstechnik, Technische Universität Dresden, 01062 Dresden

Abstract

Abstract An experimental facility for the study of boiling flows in a 3 × 3 rod bundle geometry was setup. The bundle resembles in essential geometrical parts the geometry in a pressurized water reactor fuel element. The facility is operated with a refrigerant fluid. Beside standard instrumentation for temperature, pressure and flow rate we employed particle image velocimetry for single phase flow studies, gamma ray densitometry for integral gas fraction measurement sand ultrafast X-ray tomography for the study of the void dynamics in the cross-section. Moreover extensive thermo-instrumentation allows axial rod surface temperature measurements for the central heated rod. First results will be discussed in this article.

Publisher

Walter de Gruyter GmbH

Subject

Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Radiation

Reference16 articles.

1. Sugiyama;Pressurized water reactor fuel assembly sub-channel void fraction measurement. Nucl. Technol.,1995

2. Void fraction under high pressure;low flow conditions in rod bundle geometry. Nucl. Eng. Des.,1982

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