References of "Maisberger, F."
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See detailCondensation in horizontal heat exchanger tubes
Leyer, Stephan UL; Zacharias, T.; Maisberger, F. et al

in International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012 (2012), 4

Many innovative reactor concepts for Generation III nuclear power plants use passive safety equipment for residual heat removal. These systems use two phase natural circulation. Heat transfer to the ... [more ▼]

Many innovative reactor concepts for Generation III nuclear power plants use passive safety equipment for residual heat removal. These systems use two phase natural circulation. Heat transfer to the coolant results in a density difference providing the driving head for the required mass flow. By balancing the pressure drop the system finds its operational mode. Therefore the systems depend on a strong link between heat transfer and pressure drop determining the mass flow through the system. In order to be able to analyze these kind of systems with the help of state of the art computer codes the implemented numerical models for heat transfer, pressure drop or two phase flow structure must be able to predict the system performance in a wide parameter range. Goal of the program is to optimize the numerical models and therefore the performance of computer codes analyzing passive systems. Within the project the heat transfer capacity of a heat exchanger tube will be investigated. Therefore the tube will be equipped with detectors, both temperature and pressure, in several directions perpendicular to the tube axis to be able to resolve the angular heat transfer. In parallel the flow structure of a two phase flow inside and along the tube will be detected with the help of x-ray tomography. The water cooling outside of the tube will be realized by forced convection. It will be possible to combine the flow structure measurement with an angular resolved heat transfer for a wide parameter range. The test rig is set up at the TOPLFOW facility at the Helmholtz-Zentrum Dresden-Rossendorf (HZDR), so that it will be possible to vary the pressure between 5 and 70 bar. The steam mass content will be varied between 0 and 100 percent. The results will be compared to the large scaled Emergency Condenser Tests performed at the INKA test facility in Karlstein (Germany). The paper will explain the test setup and the status of the project will be presented. [less ▲]

Detailed reference viewed: 97 (6 UL)
See detailStatus of the full scale component testing of the KERENA ™ emergency condenser and Containment Cooling Condenser
Leyer, Stephan UL; Maisberger, F.; Herbst, V. et al

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 ▲]

Detailed reference viewed: 121 (10 UL)
See detailFull scale quasi steady state component tests of the SWR 1000 emergency condenser at the INKA test facility
Leyer, Stephan UL; Maisberger, F.; Schaub, B. et al

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

[No abstract available]

Detailed reference viewed: 58 (5 UL)
See detailFull scale steady state component tests of the SWR 1000 fuel pool cooler at the INKA test facility
Leyer, Stephan UL; Maisberger, F.; Schaub, B. et al

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 ▲]

Detailed reference viewed: 84 (1 UL)