Reference : Status of the full scale component testing of the KERENA ™ emergency condenser and Co...
Scientific congresses, symposiums and conference proceedings : Paper published in a journal
Engineering, computing & technology : Mechanical engineering
http://hdl.handle.net/10993/28362
Status of the full scale component testing of the KERENA ™ emergency condenser and Containment Cooling Condenser
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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, Kaiserleistrasse 29, 63067 Offenbach, Germany]
Herbst, V. [AREVA NP GmbH, Kaiserleistrasse 29, 63067 Offenbach, Germany]
Doll, M. [AREVA NP GmbH, Kaiserleistrasse 29, 63067 Offenbach, Germany]
Wich, M. [AREVA NP GmbH, Kaiserleistrasse 29, 63067 Offenbach, Germany]
Wagner, T. [AREVA NP GmbH, Kaiserleistrasse 29, 63067 Offenbach, Germany]
2010
International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010
2
1462-1466
No
International
International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010
13 June 2010 through 17 June 2010
San Diego, CA
[en] KERENA™ (SWR1000) is an innovative boiling water reactor concept with passive safety systems. In order to verify the functionality of the passive components requiredfor the transient and accident management, the test facility INKA (Integral-Versuchstand Karlstein) is build in Karlstein (Germany). The key elements of the KERENA™ passive safety concept -the Emergency Condenser, the Containment Cooling Condenser, the Passive Core Flooding System and the Passive Pressure Pulse Transmitter - will be tested at INKA. The Emergency Condenser system transfer heaty form the reactor pressure vessel to the core flooding pools of the containment. The heat introduced into the containment during accidents will be transferred to the main heat sink for passive accident management (Shielding/Storage Pool) via the Containment Cooling Condensers. Therefore both systems are part of the passive cooling chain connecting the heat source RPV (Reactor Pressure Vessel) with the heat sink. At the INKA test facility both condensers are tested in full scale setup, in order to determine the heat transfer capacity as function of the main input parameters. For the EC these are the RPV pressure, the RPV water level, the containment pressure and the water temperature of the flooding pools. For the Containment Cooling Condenser the heat transfer capacity is a function of the containment pressure, the water temperature of the Shielding/Storage Pooland the fraction of non -condensable gases in the containment. The status of the test program and the available test data will be presented. An outlook of the future test of the passive core flooding system and the integral system test including also the passive pressure pulse transmitter will be given.
American Nuclear Society (ANS);French Nuclear Society (SFEN);Korean Nuclear Society (KNS);Atomic Energy Society of Japan (AESJ)
http://hdl.handle.net/10993/28362
81587
9781617386435

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