Full scaled tests of the KERENA trademark containment cooling condenser at the INKA test facility

in Annual meeting on nuclear technology 2010. Documentation (2010)

Status of the full scale component testing of the KERENA ™ emergency condenser and Containment Cooling Condenser

in International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010 (2010), 2

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 ... [more ▼]

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. [less ▲]

Full scale steady state component tests of the SWR 1000 fuel pool cooler at the INKA test facility

in International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009 (2009), 2

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 ... [more ▼]

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. [less ▲]

SWR 1000 integral and full scale tests of the passive safety systems

in International Conference on Advances in Nuclear Power Plants, ICAPP 2008 (2008), 1

The SWR 1000 is an innovative boiling water reactor concept with passive safety systems. In order to verify the functionality of the passive components required for the transient and accident management ... [more ▼]

The SWR 1000 is an innovative boiling water reactor concept with passive safety systems. In order to verify the functionality of the passive components required for the transient and accident management, the test facility INKA (Integral-Versuchstand Karlstein) is build up in Karlstein (Germany). The INKA test facility is designed to test the full scaled Emergency and Containment Cooling Condenser under steady state conditions as well as to simulate different postulated SWR 1000 transients and Loss of Coolant Accidents in a down scaled setup. The goal of the experiments is to obtain the power characteristics of the components and to demonstrate the ability of the passive safety systems to transfer the plant into a safe and stable state in case of a transient or LOCA. In this paper the INKA test facility setup including the tested components and the vessels, simulating the SWR 1000 containment will be described. [less ▲]

Metall-Isolator-Übergang von Lanthanhydriden: eine Kernspin-Relaxationsanalyse

Book published by Cuvillier Verlag (2004)