References of "Leyer, Stephan 50003662"
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See detailFull scale BWR containment loca response test at the INKA test facility
Wagner, T.; Leyer, Stephan UL

in International Conference on Nuclear Engineering, Proceedings, ICONE (2015), 2015-January

KERENA is an innovative boiling water reactor concept with passive safety systems (Generation III+) of AREVA. The reactor is an evolutionary design of operating BWRs (Generation II). In order to verify ... [more ▼]

KERENA is an innovative boiling water reactor concept with passive safety systems (Generation III+) of AREVA. The reactor is an evolutionary design of operating BWRs (Generation II). In order to verify the functionality and performance of the KERENA safety concept required for the transient and accident management, the test facility "Integral Teststand Karlstein" (INKA) was built at Karlstein (Germany). It is a mock-up of the KERENA boiling water reactor containment, with integrated pressure suppression system. The complete chain of passive safety components is available. The passive components and the levels are represented in full scale. The volume scaling of the containment compartments is approximately 1:24. The reactor pressure vessel (RPV) is simulated via the steam accumulator of the Karlstein Large Valve Test Facility. This vessel provides an energy storage capacity of approximately 1/6 of the KERENA RPV and is supplied by a Benson boiler with a thermal power of 22 MW. With respect to the available power supply, the containment- and system-sizing of the facility is by far the largest one of its kind worldwide. From 2009 to 2012, several single component tests were conducted (Emergency Condenser, Containment Cooling Condenser, Core Flooding System etc.). On March 21st, 2013, the worldwide first large-scale only passively managed integral accident test of a boiling water reactor was simulated at INKA. The integral test measured the combined response of the KERENA passive safety systems to the postulated initiating event was the "Main Steam Line Break" (MSLB) inside the Containment with decay heat simulation. The results of the performed integral test (MSLB) showed that the passive safety systems alone are capable to bring the plant to stable conditions meeting all required safety targets with sufficient margins. Therefore the test verified the function of those components and the interplay between them as response to an anticipated accident scenario. The test provided evidence that the INKA is worldwide the first large scale test facility to perform integral verification tests of passive safety concepts under plant-like scaling and thermodynamic conditions. Hence, the test facility also shows that it is capable to perform containment response tests for existing Generation II BWRs (with active safety systems) and advanced (passive) reactor designs besides KERENA. These test results can be used to strengthen existing containment codes with regard to heat transfer, natural circulation, gas- and temperature stratification and others. Copyright © 2015 by JSME. [less ▲]

Detailed reference viewed: 179 (11 UL)
See detailPraktische Handhabung und Kunst der Modellwahl
Unger, Jochem; Leyer, Stephan UL

in Dimensionshomogenität (2015)

Detailed reference viewed: 87 (3 UL)
See detailModell und Original
Unger, Jochem; Leyer, Stephan UL

in Dimensionshomogenität (2015)

Detailed reference viewed: 54 (0 UL)
See detailPi-Theorem
Unger, Jochem; Leyer, Stephan UL

in Dimensionshomogenität (2015)

Detailed reference viewed: 58 (2 UL)
See detailDimensionshomogenität: Erkenntnis ohne Wissen?
Unger, Jochem; Leyer, Stephan UL

Book published by Springer-Verlag (2015)

Detailed reference viewed: 95 (2 UL)
See detailMonetär-technologisches Wechselspiel
Unger, Jochem; Leyer, Stephan UL

in Dimensionshomogenität (2015)

Detailed reference viewed: 53 (0 UL)
See detailAllometrie
Unger, Jochem; Leyer, Stephan UL

in Dimensionshomogenität (2015)

Detailed reference viewed: 36 (3 UL)
See detailEffizienz der Pi Theorem Methodik
Unger, Jochem; Leyer, Stephan UL

in Dimensionshomogenität (2015)

Detailed reference viewed: 42 (1 UL)
See detailNaturkonstanten
Unger, Jochem; Leyer, Stephan UL

in Dimensionshomogenität (2015)

Detailed reference viewed: 55 (3 UL)
See detailPassive integral LOCA accident testing at Karlstein test facility
Drescher, R.; Wagner, T.; Prasser, H.-M. et al

in International Congress on Advances in Nuclear Power Plants, ICAPP 2014 (2014), 3

KERENA is an innovative boiling water reactor concept with passive safety systems (Generation III+) of AREVA . In order to verify the functionality and performance of the concept required for the ... [more ▼]

KERENA is an innovative boiling water reactor concept with passive safety systems (Generation III+) of AREVA . In order to verify the functionality and performance of the concept required for the transient and accident management, the test facility "Integral Teststand Karlstein" (INKA) was built in Karlstein (Germany). It is a mockup of the KERENA boiling water reactor containment, with integrated pressure suppression system. The complete chain of passive safety components is available. While the scaling of the passive components and the levels match the original values, the volume scaling of the containment compartments is approximately 1:24. The reactor pressure vessel (RPV) is simulated via the steam accumulator of the Karlstein Large Valve Test Facility (GAP). This vessel provides an energy storage capacity of approximately 1/6 of the KERENA RPV and is supplied by a Benson boiler with a thermal power of 22 MW. With respect to the available power supply, the containment- and system-sizing of the facility is by far the largest one of its kind worldwide. On March 21, 2013 the worldwide first large-scale, only passively managed, integral accident test of a boiling water reactor was simulated at INKA. The integral test measured the combined response of the KERENA passive safety systems to the postulated initiating event "Main Steam Line Break" (MSLB) inside the Containment with decay heat simulation. The main goals were to show the performance and the interaction of the KERENA passive safety systems, the ability to keep the core covered, to discharge the decay heat via the appropriate pathway under all circumstances and to maintain the containment within defined limits, i.e. to bring the plant to a controlled state. The performed integral test (MSLB) was being initiated via the opening of the leak at original RPV boundary conditions (75 bar reactor pressure). The leak causes a mass and energy flow from the reactor pressure vessel into the containment. The resulting drop in the RPV water level activates the Emergency Condenser, so that an additional path for energy transfer out of the RPV in parallel to the leak is opened. The pressure increase in the containment is limited via the containment pressure suppression system (short term) and the containment cooling condensers (long term). The results of the test showed that the passive safety systems alone are capable to bring the plant to stable conditions meeting all required safety targets with sufficient margins. Therefore the test verified the function of those components and the interplay between them as response to an anticipated accident scenario. The test provided evidence that the INKA is worldwide the first large scale test facility to perform integral verification tests of passive safety concepts under plant-like scaling and thermodynamic conditions. [less ▲]

Detailed reference viewed: 125 (9 UL)
See detailPassive BWR integral LOCA testing at the Karlstein test facility INKA
Drescher, Robert; Wagner, Thomas; Leyer, Stephan UL

in ATW - Internationale Zeitschrift fuer Kernenergie (2014)

Detailed reference viewed: 60 (6 UL)
See detailThe Integral Test Facility Karlstein
Leyer, Stephan UL; Wich, M.

in Science and Technology of Nuclear Installations (2012), 2012

The Integral Test Facility Karlstein (INKA) test facility was designed and erected to test the performance of the passive safety systems of KERENA, the new AREVA Boiling Water Reactor design. The ... [more ▼]

The Integral Test Facility Karlstein (INKA) test facility was designed and erected to test the performance of the passive safety systems of KERENA, the new AREVA Boiling Water Reactor design. The experimental program included single component/system tests of the Emergency Condenser, the Containment Cooling Condenser and the Passive Core Flooding System. Integral system tests, including also the Passive Pressure Pulse Transmitter, will be performed to simulate transients and Loss of Coolant Accident scenarios at the test facility. The INKA test facility represents the KERENA Containment with a volume scaling of 1:24. Component heights and levels are in full scale. The reactor pressure vessel is simulated by the accumulator vessel of the large valve test facility of Karlstein - a vessel with a design pressure of 11MPa and a storage capacity of 125 m3. The vessel is fed by a benson boiler with a maximum power supply of 22MW. The INKA multi compartment pressure suppression Containment meets the requirements of modern and existing BWR designs. As a result of the large power supply at the facility, INKA is capable of simulating various accident scenarios, including a full train of passive systems, starting with the initiating event - for example pipe rupture. Copyright © 2012 Stephan Leyer and Michael Wich. [less ▲]

Detailed reference viewed: 75 (3 UL)
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: 75 (6 UL)
See detailThe integral test facility karlstein
Leyer, Stephan UL; Wich, Michael

in Science and Technology of Nuclear Installations (2011), 2012

Detailed reference viewed: 50 (0 UL)
See detailStatus of the full scale component testing of the KERENA TM emergency condenser and Containment Cooling Condenser
Leyer, Stephan UL; Maisberger, Fabian; Herbst, Vassili et al

in Proceedings of the 2010 International Congress on Advances in Nuclear Power Plants-ICAPP'10 (2010)

Detailed reference viewed: 27 (0 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: 91 (8 UL)
See detailFull scaled tests of the KERENA trademark containment cooling condenser at the INKA test facility
Leyer, Stephan UL; Maisberger, Fabian; Lineva, Natalia et al

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

Detailed reference viewed: 58 (2 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: 67 (1 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: 37 (5 UL)
See detailSWR 1000. Integral and full-scale testing of the passive safety systems
Leyer, Stephan UL; Wich, Michael; Schaefer, Heinrich

in Annual meeting on nuclear technology 2008. Proceedings (2008)

Detailed reference viewed: 28 (0 UL)