Nikolaus Müllner

Mag.Dr. Nikolaus Müllner
Institute of Safety and Risk Sciences
Standort Dänenstraße 4, TÜWI Raum 01/08, 1190 Wien
Email nikolaus.muellner@boku.ac.at
Tel: +43 1 47654-81801, 81820

ORCID: 0000-0002-3553-5852

Meine Lehrveranstaltungen

Reactor technology Nuclear physics Computer simulation Risk research

Projekte

Es wurden 0 Projekte gefunden.

Publikationen

Wissentransfer in die Gesellschaft

Medienbeiträge

Vorträge

: 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. (Vortrag)

Autoren: Raphael Zimmerl, Lukas Anzengruber, Nikolaus Müllner

: 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics NURETH 19 2022

: 07.03.2022 - 11.03.2022 | : Online, Unknown
: 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. (Vortrag)

Autoren: Zimmerl, R.; Anzengruber, L; Müllner, N.

: 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics NURETH 19 2022

: 07.03.2022 - 11.03.2022 | : Online, Unknown
: 2021 - Assessment of Partitioning and Transmutation of High-Level Waste and Hypothetical Implementation Scenarios in Germany (Vortrag)

Autoren: Frieß, F; Liebert, W; Müllner, N

: Interdisciplinary Research Symposium on the Safety of Nuclear Disposal Practices safeND

: 10.11.2021 - 12.11.2021 | : Online
: 2019 - Severe Accident Codes (Vortrag)

Autoren: Arnold, N., Müllner, N.,

: FASTNET School

: 21.01.2019 - 25.01.2019 | : Bologna, Italy
: 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 (Vortrag)

Autoren: Kraxberger, M.; Arnold, N.; Müllner, N.

: ANS Best Estimate Plus Uncertainty International Conference (BEPU 2018)

: 13.05.2018 - 19.05.2018 | : Lucca, Italy
: 2018 - Nein zu Zwentendorf und der österreichische Antinuklearkonsens (Vortrag)

Autoren: Müllner, N.

: 9. Wiener Nuklearsymposium 2018

: 21.09.2018 | : Vienna, Austria
: 2018 - Die „International Nuclear Risk Assessment Group“ INRAG stellt sich vor - wissenschaftliche Forschung über nukleare Risiken (Vortrag)

Autoren: Müllner, N

: Für ein Europa ohne Atomkraft 4. Treffen der Allianz der Regionen für einen europaweiten Atomausstieg

: 18.09.2018 | : Linz, Austria
: 2017 - Inspection and risk assessment of sewer mains crossing lakes (Vortrag)

Autoren: Pressl, A; Plihal, H; Müllner, N; Liebert, W; Ertl, T

: 14th IWA/IAHR International Conference on Urban Drainage 2017

: 10.09.2017 - 15.09.2017 | : Prague, Czech Republic
: 2017 - Risk Analysis of Nuclear Power Plants Source Term Estimation (Poster)

Autoren: Müllner, N. ; Gufler, K.; Friess, F.; Seibert, P.

: World Bosai Forum / International Disaster Risk Conference

: 25.11.2017 - 28.11.2017 | : Sendai, Japan
: 2017 - Sicherheitsauslegung und verbundene Probleme bestehender Reaktoren: Nachrüstung auf aktuellen Stand von Wissenschaft und Technik falls „vernünftigerweise angemessen“ (Vortrag)

Autoren: Müllner, N

: 8. Wiener Nuklearsymposium 2017 - Europas alternde Kernreaktorflotte

: 15.09.2017 | : Vienna, Austria | : Wiener Umweltanwaltschaft und BOKU
: 2016 - Insights from looking at the European Core Damage Frequency (Vortrag)

Autoren: Müllner, N; Gufler, K; Sholly, S; Liebert, L;

: 80. Jahrestagung der Deutschen Physikalischen Gesellschaft DPG und DPG-Frühjahrstagung Regensburg 2016

: 06.03.2016 - 11.03.2016 | : Regensburg, Germany
: 2016 - Inspektion und Risikobewertung von Seedruckleitungen (Vortrag)

Autoren: Pressl, A.; Plihal, H.; Müllner, J.; Liebert, W.; Ertl, Th.

: 20 Jahre Kanalmanagement 2016

: 31.03.2016 | : Vienna, Austria | : ÖWAV + BOKU-SIG
: 2016 - Reaktordesigns im Wandel der Zeit, Sicherheitskonzepte Generation II/III+ Reaktoren (Vortrag)

Autoren: Müllner, N; Seidelberger, E

: FONAS-Jahrestagung 2016

: 26.09.2016 - 27.09.2016 | : Osnabrück, Germany
: 2016 - Mögliche radiologische Auswirkungen eines Versagens des Reaktordruckbehälters des KKW Tihange 2 (Vortrag)

Autoren: Arnold, N.; Gufler, K.; Sholly, S.; Müllner, N.

: Sitzung des Städteregionstages Aachen

: 27.10.2016 | : Aachen, Germany
: 2012 - Main Steam Line Break Analysis with Failure of All Main Steam Isolation Valves in a BWR (Peach Bottom) (Vortrag)

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

: 09.09.2012 - 13.09.2012 | : Kaohsiung, Taiwan, PR China
: 2012 - Adoption of the NUTEMA KM Tool for Pursuing BEPU Approach in Licensing (Vortrag)

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

: 09.09.2012 - 13.09.2012 | : Kaohsiung, Taiwan, PR China
: 2012 - NUTEMA Integrated Nuclear Knowledge Management System (Vortrag)

Autoren: Giersch, M; Camargo, C; D`Auria, F; Muellner, N

: 21st International Conference Nuclear Energy for New Europe 2012

: 05.09.2012 - 07.09.2012 | : Ljubljana, Slovenia
: 2011 - Effectiveness of core exit thermocouple (CET) temperature indication in accident management of light water reactors (Vortrag)

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

: 25.09.2011 - 29.09.2011 | : Toronto, Ontario, Canada
: 2011 - RELAP5 Based Subchannel Analysis For Licensing Of Atucha2 NPP (Vortrag)

Autoren: Muellner, N; Camusso, P; Mazzantini, O; D'Auria, F

: The 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics NURETH-14 2011

: 25.09.2011 - 29.09.2011 | : Toronto, Ontario, Canada
: 2010 - The BEPU (Best Estimate Plus Uncertainty) challenge in current licensing of nuclear reactors (Vortrag)

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

: 01.08.2010 - 05.08.2010 | : Montreal, QC, Canada
: 2010 - The Best-Estimate Plus Uncertainty (BEPU) Challenge in the Licensing of Current Generation of Reactors (Vortrag)

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

: 07.01.2010 - 08.01.2010 | : Mumbai, India
: 2010 - The BEPU (Best Estimate Plus Uncertainty) challenge in current licensing of nuclear reactors (Vortrag)

Autoren: D'Auria, F., Muellner, N., Mazzantini, O.

: 2010 ANS Annual Meeting and Embedded Topical Meetings 2010

: 13.06.2010 - 17.06.2010 | : San Diego, CA, USA
: 2010 - Evaluation of the conservatism of NPP safety analysis dose calculations as typical for licensing purposes (Vortrag)

Autoren: Nikolaus Arnold, Nikolaus Müllner, Francesco D'auria, Oscar Mazzantini

: 18th International Conference on Nuclear Engineering ICONE18 2010

: 17.05.2010 - 21.05.2010 | : Xian, PR China
: 2009 - Optimizing the initial pressure of accumulators for the Atucha2 NPP using an optimization method (Vortrag)

Autoren: Muellner, N., Del Nevo, A., Cherubini, M., D'Auria, F., Mazzantini, O.

: 17th International Conference on Nuclear Engineering ICONE17 2009

: 12.07.2009 - 16.07.2009 | : Brussels, Belgium
: 2009 - Analysis of condensation-induced water hammer in vertical geometry with RELAP5, WAHA and CODEX codes (Vortrag)

Autoren: Melikhov, O; Melikhov, V; Parfenov, Y; Davydov, M; Tiselj, I; D'Auria, F; Muellner, N

: Nuclear Energy for New Europe 2009

: 14.09.2009 - 17.09.2009 | : Bled, Slovenia
: 2009 - Addressing Boron Dilution Scenario Through RELAP5/3.3 Analysis of PWR SB LOCA (Vortrag)

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

: 12.07.2009 - 16.07.2009 | : Brussels, Belgium
: 2008 - Pressure Drop Characterization by means of a CFD Code (Vortrag)

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

: 25.05.2008 - 29.05.2008 | : Dubrovnik, Croatia
: 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 (Vortrag)

Autoren: Muellner, N; Araneo, D; Cherubini, M; D’Auria, F

: Relap5 Code Applications and Maintenance Program (CAMP) Meeting

: 28.05.2008 - 29.05.2008 | : Pisa, Italy
: 2008 - Selected Aspects of the Licensing Process of the Argentine NPP Atucha2 (Vortrag)

Autoren: Giersch, M; Galetti, R; Camargo, C; D’Auria, F; Muellner, N; Mazzantini O

: International Conference Nuclear Energy for New Europe 2008

: 08.09.2008 - 11.09.2008 | : Portoroz, Slovenia
: 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 (Vortrag)

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

: 25.05.2008 - 29.05.2008 | : Dubrovnik, Croatia
: 2007 - Relevance of Thermo-Fluid Dynamics for Establishing the Safety of Nuclear Power Plants (Vortrag)

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

: 01.06.2007 - 02.06.2007 | : Venice, Italy
: 2006 - Application of an Optimized AM Procedure followuing a SBO in a VVER1000 (Vortrag)

Autoren: Marco Cherubini, Nikolaus Muellner, Francesco D’Auria, Gianni Petrangeli

: Technical Meeting on Severe Accident and Accident Management

: 14.03.2006 - 16.03.2006 | : Tokyo, Japan
: 2006 - Accident management in VVER-1000 (Vortrag)

Autoren: D’Auria, F; Suslov, A; Muellner, N; Petrangeli, G; Cherubini, M

: 15th Pacific Basin Nuclear Conference PBNC 2006

: 15.10.2006 - 20.10.2006 | : Sydney, Australia
: 2006 - A Procedure to Optimize the Timing of Operator Actions of Accident Management Procedures (Vortrag)

Autoren: Nikolaus Muellner, Marco Cherubini, Wolfgang Kromp, Francesco D’Auria, Gianni Petrangeli

: Technical Meeting on Severe Accident and Accident Management

: 14.03.2006 - 16.03.2006 | : Tokyo, Japan
: 2006 - A Procedure to Optimize the Timing of Operator Actions of Accident Management Procedures (Vortrag)

Autoren: Nikolaus Muellner, Marco Cherubini, Wolfgang Kromp, Francesco D’Auria, Gianni Petrangeli:

: Technical Meeting on Severe Accident and Accident Management

: 14.03.2006 - 16.03.2006 | : Tokyo, Japan
: 2005 - Application of the Fast Fourier Transform Based Method (FFTBM) to Assist in the Qualification Process of the PSB-VVER Relap5 Nodalisation (Vortrag)

Autoren: Muellner, N; Seidelberger, E; Del Nevo, A; D’Auria F

: Nuclear Energy for New Europe 2005

: 05.09.2005 - 08.09.2005 | : Bled, Slovenia
: 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) (Vortrag)

Autoren: Muellner, N; Giannotti W; D' Auria, F

: 11th International Topical Meeting on Nuclear Thermal-Hydraulics (NURETH-11)

: 02.10.2005 - 06.10.2005 | : Avignon, France
: 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 (Vortrag)

Autoren: Muellner, N., Giannotti, W., D'Auria, F.

: 12th International Conference on Nuclear Engineering ICONE12 2004

: 26.04.2004 - 27.04.2004 | : Arlington, VA, USA
: 2004 - Investigation of a Possible Emergency Procedure for the VVER 440/213 NPP in Case of a Total Loss of Feedwater (Vortrag)

Autoren: Muellner, N; Giannotti, W; D’Auria, F

: Workshop on “Severe Accident Management Guidelines for VVERs”

: 12.09.2004 - 17.09.2004 | : Varna, Bulgaria
: 2004 - Investigation of H2 Generation During a SBO for a VVER 1000-320 Using the Codes RELAP5-SCDAP and MELCOR (Vortrag)

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

: 16.05.2004 - 20.05.2004 | : Dubrovnik, Croatia
: 2004 - Investigation of H2 Generation During a SBO for a VVER 1000-320 Using the Codes RELAP5-SCDAP and MELCOR (Vortrag)

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

: 16.05.2004 - 20.05.2004 | : Dubrovnik, Croatia
: 2004 - Addressing the Scaling Issue by the Thermalhydraulic System Codes: Recent Results (Vortrag)

Autoren: D'Auria, F; Cherubini, M; Galassi, G.; Muellner, N

: 5th Yugoslav Nuclear Society Conference YUNSC

: 27.09.2004 - 30.09.2004 | : Belgrade, Republic of Serbia
: 2003 - Qualification and Application of Coupled Reactor Cooling System and Containment Nodalisations (Vortrag)

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

: 26.11.2003 - 28.11.2003 | : Vienna, Austria
: 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 (Vortrag)

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”

: 20.10.2003 - 22.10.2003 | : Prague, Czech Republic

Nikolaus Müllner

Projekte

Publikationen

Wissentransfer in die Gesellschaft

Medienbeiträge

Vorträge

: 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. (Vortrag)

: 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. (Vortrag)

: 2021 - Assessment of Partitioning and Transmutation of High-Level Waste and Hypothetical Implementation Scenarios in Germany (Vortrag)

: 2019 - Severe Accident Codes (Vortrag)

: 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 (Vortrag)

: 2018 - Nein zu Zwentendorf und der österreichische Antinuklearkonsens (Vortrag)

: 2018 - Die „International Nuclear Risk Assessment Group“ INRAG stellt sich vor - wissenschaftliche Forschung über nukleare Risiken (Vortrag)

: 2017 - Inspection and risk assessment of sewer mains crossing lakes (Vortrag)

: 2017 - Risk Analysis of Nuclear Power Plants Source Term Estimation (Poster)

: 2017 - Sicherheitsauslegung und verbundene Probleme bestehender Reaktoren: Nachrüstung auf aktuellen Stand von Wissenschaft und Technik falls „vernünftigerweise angemessen“ (Vortrag)

: 2016 - Insights from looking at the European Core Damage Frequency (Vortrag)

: 2016 - Inspektion und Risikobewertung von Seedruckleitungen (Vortrag)

: 2016 - Reaktordesigns im Wandel der Zeit, Sicherheitskonzepte Generation II/III+ Reaktoren (Vortrag)

: 2016 - Mögliche radiologische Auswirkungen eines Versagens des Reaktordruckbehälters des KKW Tihange 2 (Vortrag)

: 2012 - Main Steam Line Break Analysis with Failure of All Main Steam Isolation Valves in a BWR (Peach Bottom) (Vortrag)

: 2012 - Adoption of the NUTEMA KM Tool for Pursuing BEPU Approach in Licensing (Vortrag)

: 2012 - NUTEMA Integrated Nuclear Knowledge Management System (Vortrag)

: 2011 - Effectiveness of core exit thermocouple (CET) temperature indication in accident management of light water reactors (Vortrag)

: 2011 - RELAP5 Based Subchannel Analysis For Licensing Of Atucha2 NPP (Vortrag)

: 2010 - The BEPU (Best Estimate Plus Uncertainty) challenge in current licensing of nuclear reactors (Vortrag)

: 2010 - The Best-Estimate Plus Uncertainty (BEPU) Challenge in the Licensing of Current Generation of Reactors (Vortrag)

: 2010 - The BEPU (Best Estimate Plus Uncertainty) challenge in current licensing of nuclear reactors (Vortrag)

: 2010 - Evaluation of the conservatism of NPP safety analysis dose calculations as typical for licensing purposes (Vortrag)

: 2009 - Optimizing the initial pressure of accumulators for the Atucha2 NPP using an optimization method (Vortrag)

: 2009 - Analysis of condensation-induced water hammer in vertical geometry with RELAP5, WAHA and CODEX codes (Vortrag)

: 2009 - Addressing Boron Dilution Scenario Through RELAP5/3.3 Analysis of PWR SB LOCA (Vortrag)

: 2008 - Pressure Drop Characterization by means of a CFD Code (Vortrag)

: 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 (Vortrag)

: 2008 - Selected Aspects of the Licensing Process of the Argentine NPP Atucha2 (Vortrag)

: 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 (Vortrag)

: 2007 - Relevance of Thermo-Fluid Dynamics for Establishing the Safety of Nuclear Power Plants (Vortrag)

: 2006 - Application of an Optimized AM Procedure followuing a SBO in a VVER1000 (Vortrag)

: 2006 - Accident management in VVER-1000 (Vortrag)

: 2006 - A Procedure to Optimize the Timing of Operator Actions of Accident Management Procedures (Vortrag)

: 2006 - A Procedure to Optimize the Timing of Operator Actions of Accident Management Procedures (Vortrag)

: 2005 - Application of the Fast Fourier Transform Based Method (FFTBM) to Assist in the Qualification Process of the PSB-VVER Relap5 Nodalisation (Vortrag)

: 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) (Vortrag)

: 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 (Vortrag)

: 2004 - Investigation of a Possible Emergency Procedure for the VVER 440/213 NPP in Case of a Total Loss of Feedwater (Vortrag)

: 2004 - Investigation of H2 Generation During a SBO for a VVER 1000-320 Using the Codes RELAP5-SCDAP and MELCOR (Vortrag)

: 2004 - Investigation of H2 Generation During a SBO for a VVER 1000-320 Using the Codes RELAP5-SCDAP and MELCOR (Vortrag)

: 2004 - Addressing the Scaling Issue by the Thermalhydraulic System Codes: Recent Results (Vortrag)

: 2003 - Qualification and Application of Coupled Reactor Cooling System and Containment Nodalisations (Vortrag)

: 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 (Vortrag)

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