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Dr. Alain Flores y Flores
SURO

Basic Info

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Research Keywords & Expertise

0 Nuclear Safety
0 Modelling and Simulation
0 Probabilistic safety assessment (PSA)
0 Sevre Accidents in Nuclear Power Plants
0 Hydrogen Production using Nuclear Heat

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Short Biography

Alain Flores y Flores is a senior researcher of the Research Centre Rez and Technical Support Officer of the National Radiation Protection Institute in Czech Republic. He has a degree in electric electronic engineering from the Faculty of engineer of the National Autonomous University of Mexico, Mexico. 1997-2003 He has a master’s degree in energy with a specialization in nuclear power systems from the National Autonomous University of Mexico, Mexico. 2003-2005 He holds a diploma of advanced studies from the Polytechnical University of Madrid, Spain. 2005-2007 and a PhD degree in nuclear science and technology also from the Polytechnical University of Madrid. 2007-2012 He has worked as scientific and technical support officer for the European Commission - Joint Research Centre in the Institute for Energy and Transport in The Netherlands and as Researcher for the Polytechnic University of Madrid. His research interests are focused on nuclear safety, from the development of probabilistic safety assessments to modelling and simulating of severe accidents in nuclear reactors using different computer codes as SIMMER, ASTEC, ASTEC-Na and MELCOR.

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Journal article
Published: 16 July 2021 in Sustainability
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The severe accident integral codes such as Methods for Estimation of Leakages and Consequences of Releases (MELCOR) are complex tools used to simulate and analyse the progression of a severe accident from the onset of the accident up to the release from the containment. For this reason, these tools are developed in order to simulate different phenomena coupling models which can simulate simultaneously the ThermoHydraulic (TH), the physics and the chemistry. In order to evaluate the performance in the prediction of those complicated phenomena, several experimental facilities were built in Europe and all around the world. One of these facilities is the PHEBUS built by Institut de Radioprotection et de Sûrete Nucléaire (IRSN) in Cadarache. The facility reproduces the severe accident phenomena for a pressurized water reactor (PWR) on a volumetric scale of 1:5000. This paper aims to continue the assessment of the MELCOR code from version 2.1 up to version 2.2 underlying the difference in the fission product transport. The assessment of severe accident is an important step to the sustainability of the nuclear energy production in this period where the old nuclear power plants are more than the new reactors. The analyses presented in this paper focuses on models assessment with attention on the influence of B4C oxidation on the release and transport of fission products. Such phenomenon is a concern point in the nuclear industry, as was highlighted during the Fukushima Daiichi accident. Simulation of the source term is a key point to evaluate the severe accident hazard along with other safety aspects.

ACS Style

Alain Flores Y Flores; Danilo Ferretto; Tereza Marková; Guido Mazzini. Analysis of Release Model Effect in the Transport of Fission Products Simulating the FPT3 Test Using MELCOR 2.1 and MELCOR 2.2. Sustainability 2021, 13, 7964 .

AMA Style

Alain Flores Y Flores, Danilo Ferretto, Tereza Marková, Guido Mazzini. Analysis of Release Model Effect in the Transport of Fission Products Simulating the FPT3 Test Using MELCOR 2.1 and MELCOR 2.2. Sustainability. 2021; 13 (14):7964.

Chicago/Turabian Style

Alain Flores Y Flores; Danilo Ferretto; Tereza Marková; Guido Mazzini. 2021. "Analysis of Release Model Effect in the Transport of Fission Products Simulating the FPT3 Test Using MELCOR 2.1 and MELCOR 2.2." Sustainability 13, no. 14: 7964.

Journal article
Published: 15 September 2020 in Nuclear Engineering and Design
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The Fukushima Daiichi NPP (Nuclear Power Plant) accident pointed out the hydrogen explosion issue as one of the main problems that can affect the NPP containment integrity. During a severe accident scenario, the hydrogen combustion can occur and lead to containment integrity failure, since it generates local and global pressure and heat spikes. Such topic was analysed in several research programs addressed all around the world. An important series of test campaigns was done in OECD/NEA WGAMA (Organisation for Economic Co-operation and Development/Nuclear Energy Agency Working Group on Analysis and Management of Accidents) program called THAI (Thermal-hydraulics, Hydrogen, Aerosol and Iodine). The THAI goal is to simulate several phenomena related on hydrogen and Fission Product behaviour in the containment to obtain data relevant for the code benchmarking and validation. Therefore, theoretical analyses are needed, in order to obtain a reliable prediction of the accidental scenario. The facility allows to investigate safety relevant effects under thermal-hydraulics conditions of severe accidents. The experiments performed cover from hydrogen deflagration to iodine and aerosol behaviour under different thermal-hydraulics conditions. Three representative experiments were chosen from the THAI campaign to be modeled and simulated using the MELCOR code with versions 2.1 and 2.2 and compare the results with the experimental ones. This work aims to assess the MELCOR code capability pointing out on the limitation in simulating the hydrogen deflagration and underling possible method to reduce their effect on the simulate results. The benchmarks were addressed with old version of MELCOR however the new version presented slightly different results due to the modification in the parametric model and the default sensitivity coefficients.

ACS Style

A. Flores Y Flores; G. Mazzini. Analyses of THAI 1 hydrogen deflagration using MELCOR code version 2.1 and 2.2. Nuclear Engineering and Design 2020, 369, 110838 .

AMA Style

A. Flores Y Flores, G. Mazzini. Analyses of THAI 1 hydrogen deflagration using MELCOR code version 2.1 and 2.2. Nuclear Engineering and Design. 2020; 369 ():110838.

Chicago/Turabian Style

A. Flores Y Flores; G. Mazzini. 2020. "Analyses of THAI 1 hydrogen deflagration using MELCOR code version 2.1 and 2.2." Nuclear Engineering and Design 369, no. : 110838.

Journal article
Published: 06 August 2020 in Journal of Nuclear Engineering and Radiation Science
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In order to develop an appropriate knowledge to support the SUJB (State Office of Nuclear Safety), the CVR (Research Centre Rež), in collaboration with SURO (National Radiation Protection Institute) is developing a methodology to simulate nuclear power plants under accidental conditions. A particular effort is focused in the severe accident phenomenology where hydrogen deflagration carries a critical issue for the containment integrity, such as Fukushima Daiichi accident. For this purpose, THAI (Thermal-hydraulics, hydrogen, aerosol and iodine) experimental campaigns are chosen due to the several tests involved in different conditions. THAI containment test facility is used to open questions concerning the behaviour of hydrogen, iodine and aerosols in the containment of water-cooled reactors during severe accidents. The Fukushima Daiichi Accident demonstrates that the hydrogen deflagration could lead to a significant containment damage. For this reason, a particular attention is given to the hydrogen deflagration scenario. All simulations are prepared and modelled in MELCOR 2.1. The results obtained showed a strong influence related with some factors as: the nodalization pattern, control volume number (CV), flow paths number FP and time step. In order to assess the THAI model with the THAI final reports, a sensitivity analysis focused with those parameters was performed.

ACS Style

Alain Flores Y Flores; Guido Mazzini. Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code. Journal of Nuclear Engineering and Radiation Science 2020, 1 .

AMA Style

Alain Flores Y Flores, Guido Mazzini. Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code. Journal of Nuclear Engineering and Radiation Science. 2020; ():1.

Chicago/Turabian Style

Alain Flores Y Flores; Guido Mazzini. 2020. "Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code." Journal of Nuclear Engineering and Radiation Science , no. : 1.

Journal article
Published: 19 April 2019 in Journal of Nuclear Engineering and Radiation Science
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This work describes the computer model development of the water–water energetic reactor (VVER) 1000 nuclear power plant (NPP) in the methods for estimation of leakages and consequences of releases (MELCOR) 1.8.6 code and its subsequent use for the accident scenarios analysis leading to the core melting. The baseline accident scenario was a stress test case—the station blackout (SBO, the complete loss of alternating current electric power in a nuclear power plant). In addition to this, four other scenarios were analyzed in which the SBO was combined with other technological failures—the loss of steam generator feedwater system and small, medium, and large break coolant accidents (LOCA). The results provided detailed information on the time course of accident scenarios, their temperature and pressure parameters, hydrogen production, and the mass inventory released from the molten corium and debris into the containment of the NPP.

ACS Style

Marek Ruscak; Guido Mazzini; Milos Kyncl; Sevastyan Savanyuk; Miroslav Hrehor; Alis Musa; Alain Flores Y Flores. VVER 1000 Severe Accident Analyses Using MELCOR Code. Journal of Nuclear Engineering and Radiation Science 2019, 5, 1 .

AMA Style

Marek Ruscak, Guido Mazzini, Milos Kyncl, Sevastyan Savanyuk, Miroslav Hrehor, Alis Musa, Alain Flores Y Flores. VVER 1000 Severe Accident Analyses Using MELCOR Code. Journal of Nuclear Engineering and Radiation Science. 2019; 5 (3):1.

Chicago/Turabian Style

Marek Ruscak; Guido Mazzini; Milos Kyncl; Sevastyan Savanyuk; Miroslav Hrehor; Alis Musa; Alain Flores Y Flores. 2019. "VVER 1000 Severe Accident Analyses Using MELCOR Code." Journal of Nuclear Engineering and Radiation Science 5, no. 3: 1.