Reference : Full scale steady state component tests of the SWR 1000 fuel pool cooler at the INKA ...
Scientific congresses, symposiums and conference proceedings : Paper published in a journal
Engineering, computing & technology : Mechanical engineering
http://hdl.handle.net/10993/28357
Full scale steady state component tests of the SWR 1000 fuel pool cooler at the INKA test facility
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Leyer, Stephan mailto [University of Luxembourg > Faculty of Science, Technology and Communication (FSTC) > Engineering Research Unit]
Maisberger, F. [AREVA NP GmbH, Offenbach, Germany]
Schaub, B. [AREVA NP GmbH, Offenbach, Germany]
Brettschuh, W. [AREVA NP GmbH, Offenbach, Germany]
Doll, M. [AREVA NP GmbH, Offenbach, Germany]
Wich, M. [AREVA NP GmbH, Offenbach, Germany]
Schäfer, H. [AREVA NP GmbH, Offenbach, Germany]
Unger, J. [TU Darmstadt, Germany]
2009
International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
Atomic Energy Society of Japan
2
1629-1633
No
International
International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009
10 May 2009 through 14 May 2009
[en] Cooling ; Cooling systems ; Cooling water ; Fuels ; Heat exchangers ; Heat transfer ; Lakes ; Nuclear power plants ; Temperature ; Test facilities ; Water supply ; Cooling components ; Cooling water temperature ; Forced circulations ; Plant operations ; Postulated accidents ; Reactor building ; Transfer capacities ; Tubular heat exchangers ; Fuel storage
[en] The SWR 1000 fuel pool coolers are tubular heat exchangers. They are installed on the fuel pool wall around the spent fuel storage racks. Fuel pool water is cooled by means of natural convection. Forced circulation flow of closed-cooling water exists on the tube side of each heat exchanger. The penetrations of the cooling water supply lines through the fuel pool liner are all located above the pool water surface. This ensures that the fuel pool cannot lose water in the event of a pipe break. Integration of the cooling components inside the fuel pool ensures only noncontaminated piping within the reactor building. The fuel pool cooling system consists of two redundant cooling trains. Each cooling train comprises four heat exchangers connected in parallel. The system must ensure adequate heat removal both during normal plant operation and in the event of any postulated accident. To verify proper functioning of the component, full-scale, steadystate tests were performed at the INKA (Integral Teststand Karlstein) test facility in Karlstein Germany. The characteristic diagram for heat transfer capacity of the component as a function of cooling water temperature and fuel pool water temperature obtained from these experiments will be presented in this paper.
http://hdl.handle.net/10993/28357
108003
9781617386084

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