Nikolaus Müllner
Mag. Dr. Nikolaus Müllner
Institut Institute of Safety and Risk Sciences
Location Dänenstraße 4, TÜWI Raum 01/08, 1190 Wien
Email nikolaus.muellner@boku.ac.at
Tel: +43 1 47654-81801, 81820
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Publications
Knowledge Transfer to Society
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Lectures
(2022) CODE TO EXPERIMENT COMPARISON OF A STEAM GENERATOR HOT HEADER BREAK AT PSB-VVER TEST FACILITY WITH RELAP5/SCDAPSIM 4.1 THERMAL HYDRAULIC SYSTEM CODE.
Autoren: Raphael Zimmerl, Lukas Anzengruber, Nikolaus Müllner
19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics NURETH 19 2022
(2022) CODE TO EXPERIMENT COMPARISON OF A STEAM GENERATOR HOT HEADER BREAK AT PSB-VVER TEST FACILITY WITH RELAP5/SCDAPSIM 4.1 THERMAL HYDRAULIC SYSTEM CODE.
Autoren: Zimmerl, R.; Anzengruber, L; Müllner, N.
19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics NURETH 19 2022
(2021) Assessment of Partitioning and Transmutation of High-Level Waste and Hypothetical Implementation Scenarios in Germany
Autoren: Frieß, F; Liebert, W; Müllner, N
Interdisciplinary Research Symposium on the Safety of Nuclear Disposal Practices safeND
(2019) Severe Accident Codes
Autoren: Arnold, N., Müllner, N.,
FASTNET School
(2018) Effects of heat transfer models on RPV failure during a Station Blackout Scenario at a VVER1000 in MELCOR 1.8.5 and MELCOR 1.8.6
Autoren: Kraxberger, M.; Arnold, N.; Müllner, N.
ANS Best Estimate Plus Uncertainty International Conference (BEPU 2018)
(2018) Nein zu Zwentendorf und der österreichische Antinuklearkonsens
Autoren: Müllner, N.
9. Wiener Nuklearsymposium 2018
(2018) Die „International Nuclear Risk Assessment Group“ INRAG stellt sich vor - wissenschaftliche Forschung über nukleare Risiken
Autoren: Müllner, N
Für ein Europa ohne Atomkraft 4. Treffen der Allianz der Regionen für einen europaweiten Atomausstieg
(2017) Inspection and risk assessment of sewer mains crossing lakes
Autoren: Pressl, A; Plihal, H; Müllner, N; Liebert, W; Ertl, T
14th IWA/IAHR International Conference on Urban Drainage
(2017) Risk Analysis of Nuclear Power Plants Source Term Estimation
Autoren: Müllner, N. ; Gufler, K.; Friess, F.; Seibert, P.
World Bosai Forum / International Disaster Risk Conference
(2017) Sicherheitsauslegung und verbundene Probleme bestehender Reaktoren: Nachrüstung auf aktuellen Stand von Wissenschaft und Technik falls „vernünftigerweise angemessen“
Autoren: Müllner, N
8. Wiener Nuklearsymposium 2017 - Europas alternde Kernreaktorflotte
(2016) Insights from looking at the European Core Damage Frequency
Autoren: Müllner, N; Gufler, K; Sholly, S; Liebert, L;
80. Jahrestagung der Deutschen Physikalischen Gesellschaft DPG und DPG-Frühjahrstagung Regensburg 2016
(2016) Inspektion und Risikobewertung von Seedruckleitungen
Autoren: Pressl, A.; Plihal, H.; Müllner, J.; Liebert, W.; Ertl, Th.
20 Jahre Kanalmanagement 2016
(2016) Reaktordesigns im Wandel der Zeit, Sicherheitskonzepte Generation II/III+ Reaktoren
Autoren: Müllner, N; Seidelberger, E
FONAS-Jahrestagung 2016
(2016) Mögliche radiologische Auswirkungen eines Versagens des Reaktordruckbehälters des KKW Tihange 2
Autoren: Arnold, N.; Gufler, K.; Sholly, S.; Müllner, N.
Sitzung des Städteregionstages Aachen
(2012) Main Steam Line Break Analysis with Failure of All Main Steam Isolation Valves in a BWR (Peach Bottom)
Autoren: M. Lanfredini, N. Muellner, F. D’Auria, N. Arnold, S. Sholly, W. Kromp
9th International Topical Meeting on Nuclear Thermal-Hydraulics NUTHOS-9 2012 - Operation and Safety
(2012) Adoption of the NUTEMA KM Tool for Pursuing BEPU Approach in Licensing
Autoren: Muellner, N; Martinucci, M; Tambasco, P; D'Amato, R; Camargo, C; D’Auria F
9th International Topical Meeting on Nuclear Thermal-Hydraulics NUTHOS-9 2012 - Operation and Safety
(2012) NUTEMA Integrated Nuclear Knowledge Management System
Autoren: Giersch, M; Camargo, C; D`Auria, F; Muellner, N
21st International Conference Nuclear Energy for New Europe 2012
(2011) Effectiveness of core exit thermocouple (CET) temperature indication in accident management of light water reactors
Autoren: Nakamura, H; Toth, I; Sandervag, O; Umminger, K; Dreier, J; Prior, R; Ramon Alonso, J; Muellner, N; D'Auria, F; Amri, A; Muehleisen, A
The 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics NURETH-14 2011
(2011) RELAP5 Based Subchannel Analysis For Licensing Of Atucha2 NPP
Autoren: Muellner, N; Camusso, P; Mazzantini, O; D'Auria, F
The 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics NURETH-14 2011
(2010) The BEPU (Best Estimate Plus Uncertainty) challenge in current licensing of nuclear reactors
Autoren: D’Auria, F; Mazzantini, O; Muellner, N; Petruzzi, A
3rd Joint US-European Fluids Engineering Summer Meeting ASME and 8th International Conference on Nanochannels, Microchannels and Minichannels 2010
(2010) The Best-Estimate Plus Uncertainty (BEPU) Challenge in the Licensing of Current Generation of Reactors
Autoren: D’Auria, F; Mazzantini, O; Muellner, N
The International Workshop on New Horizons in Nuclear Reactor Thermal Hydraulics and Safety, Atomic Energy Regulatory Board, India
(2010) The BEPU (Best Estimate Plus Uncertainty) challenge in current licensing of nuclear reactors
Autoren: D'Auria, F., Muellner, N., Mazzantini, O.
2010 ANS Annual Meeting and Embedded Topical Meetings 2010
(2010) Evaluation of the conservatism of NPP safety analysis dose calculations as typical for licensing purposes
Autoren: Nikolaus Arnold, Nikolaus Müllner, Francesco D'auria, Oscar Mazzantini
18th International Conference on Nuclear Engineering ICONE18 2010
(2009) Optimizing the initial pressure of accumulators for the Atucha2 NPP using an optimization method
Autoren: Muellner, N., Del Nevo, A., Cherubini, M., D'Auria, F., Mazzantini, O.
17th International Conference on Nuclear Engineering ICONE17 2009
(2009) Analysis of condensation-induced water hammer in vertical geometry with RELAP5, WAHA and CODEX codes
Autoren: Melikhov, O; Melikhov, V; Parfenov, Y; Davydov, M; Tiselj, I; D'Auria, F; Muellner, N
Nuclear Energy for New Europe 2009
(2009) Addressing Boron Dilution Scenario Through RELAP5/3.3 Analysis of PWR SB LOCA
Autoren: Pla, P., Galetti, R., D'Auria, F., Parisi, C., Giannotti, W., Del Nevo, A., Muellner, N., Reventós, F.
17th International Conference on Nuclear Engineering ICONE17 2009
(2008) Pressure Drop Characterization by means of a CFD Code
Autoren: Araneo, D; Pla, P; Moretti, F; D’Auria, F; Muellner, N
7th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids 2008
(2008) Effect of SG Modelling on Primary Side Pressure and Temperature Trend During Long Term Station Black Out Conditions in VVER Using Relap5 and Cathare2 System Code
Autoren: Muellner, N; Araneo, D; Cherubini, M; D’Auria, F
Relap5 Code Applications and Maintenance Program (CAMP) Meeting
(2008) Selected Aspects of the Licensing Process of the Argentine NPP Atucha2
Autoren: Giersch, M; Galetti, R; Camargo, C; D’Auria, F; Muellner, N; Mazzantini O
International Conference Nuclear Energy for New Europe 2008
(2008) Effect of SG Modelling on Primary Side Pressure and Temperature Trend during Long Term Station Black Out Conditions in VVER using Relap5 and Cathare2 System Codes
Autoren: Muellner, N; Araneo, D; Cherubini, M; D’Auria, F
7th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids 2008
(2007) Relevance of Thermo-Fluid Dynamics for Establishing the Safety of Nuclear Power Plants
Autoren: D'Auria, F; Cherubini, M; Muellner, N
32nd Congress of the International Association of Hydraulic Engineering and Research IAHR 2007 - Harmonizing the demands of art and nature in hydraulics
(2006) Application of an Optimized AM Procedure followuing a SBO in a VVER1000
Autoren: Marco Cherubini, Nikolaus Muellner, Francesco D’Auria, Gianni Petrangeli
Technical Meeting on Severe Accident and Accident Management
(2006) Accident management in VVER-1000
Autoren: D’Auria, F; Suslov, A; Muellner, N; Petrangeli, G; Cherubini, M
15th Pacific Basin Nuclear Conference PBNC 2006
(2006) A Procedure to Optimize the Timing of Operator Actions of Accident Management Procedures
Autoren: Nikolaus Muellner, Marco Cherubini, Wolfgang Kromp, Francesco D’Auria, Gianni Petrangeli
Technical Meeting on Severe Accident and Accident Management
(2006) A Procedure to Optimize the Timing of Operator Actions of Accident Management Procedures
Autoren: Nikolaus Muellner, Marco Cherubini, Wolfgang Kromp, Francesco D’Auria, Gianni Petrangeli:
Technical Meeting on Severe Accident and Accident Management
(2005) Application of the Fast Fourier Transform Based Method (FFTBM) to Assist in the Qualification Process of the PSB-VVER Relap5 Nodalisation
Autoren: Muellner, N; Seidelberger, E; Del Nevo, A; D’Auria F
Nuclear Energy for New Europe 2005
(2005) Relap5 Analysis of an Eop based on Mobile Pumps, at a Generic VVER-1000 NPP in case of a Total Loss of the Primary Heat Sink (for DBDA Conditions)
Autoren: Muellner, N; Giannotti W; D' Auria, F
11th International Topical Meeting on Nuclear Thermal-Hydraulics (NURETH-11)
(2004) Investigation of a Possible Emergency Procedure for the VVER 1000 NPP in Case of a Total Loss of Feedwater and a Main Steam Line Break
Autoren: Muellner, N., Giannotti, W., D'Auria, F.
12th International Conference on Nuclear Engineering ICONE12 2004
(2004) Investigation of a Possible Emergency Procedure for the VVER 440/213 NPP in Case of a Total Loss of Feedwater
Autoren: Muellner, N; Giannotti, W; D’Auria, F
Workshop on “Severe Accident Management Guidelines for VVERs”
(2004) Investigation of H2 Generation During a SBO for a VVER 1000-320 Using the Codes RELAP5-SCDAP and MELCOR
Autoren: N. Muellner, W. Giannotti, F. D’Auria, G. Kastchiev and W. Kromp
5th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids 2004
(2004) Investigation of H2 Generation During a SBO for a VVER 1000-320 Using the Codes RELAP5-SCDAP and MELCOR
Autoren: Muellner, N., W. Giannotti, F. D’Auria, G. Kastchiev and W. Kromp
5th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids 2004
(2004) Addressing the Scaling Issue by the Thermalhydraulic System Codes: Recent Results
Autoren: D'Auria, F; Cherubini, M; Galassi, G.; Muellner, N
5th Yugoslav Nuclear Society Conference YUNSC
(2003) Qualification and Application of Coupled Reactor Cooling System and Containment Nodalisations
Autoren: F. D’Auria, G.M. Galassi, W. Giannotti, A. Petruzzi, K. Moussavian, F. Pierro, A. Lo Nigro and N. Muellner
IAEA Technical Meeting 2003 - Progress in Development and Use of Coupled Codes for Accident Analysis
(2003) Investigation of possible emergency procedure for the VVER-1000 NPP in case of a total loss of feedwater and a main steam line break
Autoren: N. Muellner, A. Petruzzi, W. Giannotti and F. D’Auria
IAEA Technical Meeting to “Monitor Progress in Implemention of Accident Management Programmes at NPPs”