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ESF-3D - Energy reduction for safe battery production through innovative networking of information and manufacturing technologies; sub-project: Research into the fluidic and functional properties of the 3D manufactured functional unit, BMBF/PTJ, FKZ 03WIR2716E, Duration: 01.03.2023 - 31.12.2025
Generic thermohydraulic and physicochemical analyses for the implementation of an ATHLET module for the simulation of thermohydraulic consequences of zinc borate deposits in the PWR core (AZora), BMWi, FKZ 150 1585, duration: 01.02.2019-31.01.2022
Local effects in the PWR core due to zinc borate deposits after KMV, BMWi, FKZ 150 1491, Duration: 01.03.2015 - 31.10.2018
Particle formation and transport in the core of pressurized water reactors - thermal and fluid dynamic mechanisms (Phase 1 & 2), BMWi, FKZ 150 1431/150 1468, Duration: 01.04.2012 - 31.12.2014
Insulation material-loaded coolant flow in the core - experimental investigations and data analysis, BMWi, FKZ 150 1360, Duration: 01.10.2008 - 31.03.2012
Particle-loaded coolant flow in the sump and in the condensation chamber - Experiments and CFD simulation, BMWi, FKZ 150 1307, Duration: 01.07.2005 - 31.12.2009
Investigation of the behavior of released insulation material in a coolant flow
(coolant flow with solid particles), BMWi, FKZ 150 1270, Duration: 01.07.2002 - 30.06.2007
Harm, U.; Kryk, H.; Hampel, U.; Seeliger, A.; Alt, S.; Kästner, W.: Lab Scale Experimental Studies For Modeling Possible Zinc Removal Efforts in LOCA Situations. Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), 2022, Brussels, Belgium
Kästner, W.; Alt, S.; Seeliger, A.; Zacharias, F.; Harm, U.; Illgen, R.; Hampel, U. & Kryk, H.: Modelling thermal-hydraulic effects of zinc borate deposits in the PWR core after LOCA - Experimental strategies and test facilities, atw 6/7 2020, KERNTECHNIK 2020 Special, 2020
Renger, S.; Alt, S.; Gocht, U.; Kästner, W.; Seeliger, A.; Kryk, H.; Harm, U.: Multiscaled Experimental Investigations of Corrosion and Precipitation Processes After Loss-of-Coolant Accidents in Pressurized Water Reactors. Nuclear Technology, 2018, 205, 248-261
Kryk, H.; Kästner, W.; Hampel, U.; Seeliger, A.: Chemical Effects in Loss-of-Coolant Accidents in Pressurized Water Reactors - Work of the Competence Center East for Nuclear Technology, Proceedings of the Power Plant Technology Colloquium, 2017
Seeliger, A.; Alt, S.; Kästner, W.; Renger, S.; Kryk, H.; Harm, U.: Zinc corrosion after loss-of-coolant accidents in pressurized water reactors - Thermo- and fluiddynamic effects. Nuclear Engineering and Design, 2016, 305, 489-502
Hoffmann, W.; Kryk, H.; Seeliger, A.; Kästner, W.; Alt, S.; Renger, S.: Zinc corrosion after loss-of-coolant accidents in pressurized water reactors - Physicochemical effects. Nuclear Engineering and Design, 2014, 280, 570-578
Seeliger, A.: Novel methods for the determination of simulation parameters for the CFD simulation of particle-laden flows, dissertation, TU Ilmenau, 2010
