Deputy Director for Engineering. Nuclear Safety Directorate.
CSN
Michela Angelucci
Hiroki Asatsuma
Student
The University of Tokyo
Helena Aubets
PhD student
KTH Royal Institute of Technology
Kwang-Hyun Bang
Félix Barrio
Head of the International Relations Division
CIEMAT
Satish Basnet
Sevostian Bechta
Ahmed BENTAIB
Senior researcher
ASNR
Ahmed Bentaib
Nuclear safety specialist
OECD-NEA
Rafael Bocanegra Melian
Senior Engineer
ENSO
Lourdes Borondo
Head of the Safety and Quality Unit
Cofrentes Nuclear Power Plant, operated by Iberdrola Generación Nuclear
Matthias Braun
Stephan Brumm
Scientific Officer
European Commission JRC
Michael Buck
Head,Reactor Safety Division
Institute for Nuclear Technology and Energy Systems, University of Stuttgart
Laure Carenini
-
Autorité de sûreté nucléaire et de radioprotection, France
Mauricio Cazado
Research Scientist
Karlsruhe Institute of Technology
JUN SUNG CHOI
PhD candidate
Seoul National University
Erik Cilia
ENEA
Behnam Dastvareh
Kevin Dieter
Yoichi Endo
Björn Engström
Róbert Farkas
Mitchell Farmer
Manager Light Water Reactor Programs
argonne national lab
Florian Fichot
Joan Fontanet
Jonathan Fowles
Toyoshi Fuketa
Fabrizio Gabrielli
Deputy Group Leader
Karlsruhe Institute of Technology
MÓNICA GARCÍA MARTÍN
Researcher
CIEMAT
Alberto García-Herranz
Pre-doctoral Researcher
Universidad Politécnica de Madrid (UPM)
Lee Gardner
Fabio Giannetti
Amparo Giner Gonzalez
OPERATION & TECHNICAL TRAINING MANAGER
Westinghouse Electric Company
Anne Cécile Gregoire
Sanjeev Gupta
-
Independent expert
JAEHYUN HAM
KumHo Han
Associate Manager
FNC Technology
Jens Hermann
Luis Enrique Herranz
Head of the Unit of Nuclear Safety Research
CIEMAT
Luis E. Herranz
Head of the Unit of Nuclear Safety
CIEMAT
Luis E. HERRANZ
Head of the Unit for Nuclear Safety Research
CIEMAT
Luis Enrique Herranz
CIEMAT
Thorsten Hollands
Head of Containment Department
Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH
Mikko Ilvonen
Senior Scientist
VTT Nuclear Energy, Finland
Angelgiorgo Iorizzo
PO
European Commission, RTD, Euratom Research
Gonzalo Jimenez
Zaira Itzel Jiménez Balbuena
Student
Karlsruhe Institute of Technology
Bouchain Joâo
Christophe Journeau
Algirdas Kaliatka
Teemu Kärkelä
Wataru Kikuchi
Researcher
Nuclear Regulation Authority, JAPAN
Ju Bin Kim
Ph. D. Student
Seoul National University
Ivo Kljenak
Scientific councillor
Jozef Stefan Institute
Yuma Kobayashi
Graduate Student
Graduate School of Advanced Science and Engineering Waseda University
Mikhail Kolesnik
Jan Komrska
Researcher, PhD Student
Czech Technical University - Faculty of Mechanical Engineering
AT KHEN Kresna
Florian Krist
Research Associate
Ruhr-Universität Bochum, Plant Simulation and Saftey
Minchan Kwon
Ph. D. Student
Seoul National University
xiangyu li
Xin Li
Nan Li
Beijing,China
China Nuclear Power Engineering Co., Ltd
Terttaliisa Lind
-
Paul Scherrer Institute, Switzerland
Liviusz Lovasz
Chief Expert for Core Degradation
GRS
Chuanhe Lu
David L. Luxat
Sandia National Laboratories
Livia M.-Tiborcz
Technical Expert
Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH
Mateusz Malicki
Paul Scherrer Institute
Mateusz Malicki
Scientist
Paul Scherrer Institut
Principato Marcello
PhD student
Sapienza University of Rome
Claire Marshall
MARIANO MARTIN GARCIA
Fulvio Mascari
Senior Researcher
ENEA
Tomonari Mashiko
Paul McMinn
Lead Engineer
Westinghouse
Alexei Miassoedov
Nuclear Engineer working on advanced water-cooled reactors
International Atomic Energy Agency
Bénédicte MICHEL
Research engineer
ASNR
Raphaël MONOD
Andrew Morreale
Technical Manager - Reactor Safety
Canadian Nuclear Laboratories (CNL)
Onur Murat
Research Scientist
Karlsruhe Institute of Technology
Youngsu Na
Yosuke NISHIMURA
Sandro Paci
University of Pisa
Peter Pandazis
Giacomo Petrosillo
PhD Student
CEA
Pascal Piluso
-
Commissariat à l’énergie atomique et aux énergies alternatives, CEA, France
Fengyang QUAN
Senior Engineer
China Nuclear Power Engineering CO., LTD
Alvaro Ramos Perez
PhD student
PSI
Ernst-Arndt Reinecke
Department Head
Forschungszentrum Juelich GmbH
Ernst-Arndt Reinecke
Clavier Rémi
Nicole Richter
Research assistant
Ruhr-Universität Bochum, Plant Simulation and Safety Group (PSS)
Rodrigo Rivilla
Universidad Politécnica de Madrid
Federico Rocchi
LE TELLIER Romain
Miguel Sánchez
Head of the Modeling and Simulation Area
Nuclear Safety Council (CSN)
Nathalie SEILER
LUIS SERRA LOPEZ
Tuomo Sevón
KENTA SHIMOMURA
Researcher
Japan Atomic Energy Agency
Donggun Son
Sidi M. O. Souvi
Researcher
ASNR
Anastasia Stakhanova
Wissenschaftlicher Mitarbeiterin
Karlsruhe Institute of Technology
Martin Steinbrück
Group leader
Karlsruhe Institute of Technology (KIT)
Kelm Stephan
Agustin Tanarro Onrubia
Principal Engineer
Westinghouse
Štěpán Tichý
Giacomo Tinfena
Petr Vácha
Head of Severe Accidents Department
UJV Rez, a.s.
Mindaugas Valinčius
Senior Research Associate
Lithuanian Energy Institute
Carlos Vázquez-Rodríguez
Alejandro VILLARREAL LARRAURI
Yuriy Vorobyov
Gaus-Liu Xiaoyang
Ruicong XU
Ryo Yokoyama
Julie-Anne Zambaux
Engineer
ASNR
Lu Zhao
DAWEI ZHAO
Tipo de sesión: Welcome
Registration
18 Mayo
Tipo de sesión: Welcome
Welcome and opening
18 Mayo
Modera
Sandro Paci
University of Pisa
Fabrizio Gabrielli
Deputy Group Leader
Karlsruhe Institute of Technology
.
Félix Barrio
Head of the International Relations Division
CIEMAT
Santiago Aleza Enciso
Deputy Director for Engineering. Nuclear Safety Directorate.
CSN
Luis E. HERRANZ
Head of the Unit for Nuclear Safety Research
CIEMAT
Tipo de sesión: Plenary Sessions
Plenary Session 1 – SINGULAR CAREERS IN THE SEVERE ACCIDENT RESEARCH
18 Mayo
Modera
Terttaliisa Lind
-
Paul Scherrer Institute, Switzerland
30 years of materials science for nuclear safety. From unexpected findings to improved severe accident codes
Martin Steinbrück
Group leader
Karlsruhe Institute of Technology (KIT)
Research, Insights, and Lessons Learned During a Career Focused on Ex-Vessel Severe Accident Behavior
Mitchell Farmer
Manager Light Water Reactor Programs
argonne national lab
Tipo de sesión: Oral communications
Session 1.1 Severe Accident Scenarios
18 Mayo
Room-1.A.01
Modera
Michela Angelucci
David L. Luxat
Sandia National Laboratories
Analysis of dose rates in the containment during the Fukushima accident
Tuomo Sevón
Preliminary Analytical Justification of Long-Term Containment Cooling System with Steam Condensing Heat Exchanger for NPPs with VVER-1000 Reactors
Yuriy Vorobyov
ASTEC Modelling of the AP1000 and Cold-Leg Small-Break LOCA Simulations with Long-Term Cooling Cut-off
DAWEI ZHAO
Instrumentation survivability Assessment during a Severe Accident; Incorporating radiation monitoring in MELCOR to evaluate the impact on SAMGs
Rodrigo Rivilla
Universidad Politécnica de Madrid
Tipo de sesión: Oral communications
Session 2.1 In-vessel Corium and debris coolability
18 Mayo
Room-1.A.04
Modera
Laure Carenini
-
Autorité de sûreté nucléaire et de radioprotection, France
Matthias Braun
Reflooding of a damaged core in case of severe accident: synthesis of experimental results, modelling and consequences for the reactor scale
Florian Fichot
Simulation of the low Prandtl metallic layer of a corium pool
Nathalie SEILER
Analysis of In-Vessel Retention in a VVER-1000 Reactor Design using AC2
Peter Pandazis
High fidelity numerical simulation of In-vessel corium pool under severe accident scenarios
Abdullah Alasif
Tipo de sesión: Oral communications
Session 3.1 Severe Accident Scenarios: Small Modular Reactors
18 Mayo
Auditorio
Modera
MÓNICA GARCÍA MARTÍN
Researcher
CIEMAT
Fulvio Mascari
Senior Researcher
ENEA
ANALYSIS OF POSTULATED SEVERE ACCIDENTS IN GENERIC INTEGRAL PWR SMALL MODULAR REACTORS: OUTCOMES ON INTEGRAL CODES’ MODELLING CAPABILITIES FROM THE HORIZON EURATOM SASPAM-SA PROJECT
Mauricio Cazado
Research Scientist
Karlsruhe Institute of Technology
Rolls-Royce SMR 3D Hydrogen Combustion Assessment Approach
Jonathan Fowles
Severe accident analysis of SASPAM-SA Design II LW-SMR dry containment using containmentFOAM
Carlos Vázquez-Rodríguez
Analysis of LDR Lite Reactor's Resistance to Severe Accidents
Algirdas Kaliatka
Tipo de sesión: Oral communications
Session 4.1 Ex-vessel Corium and debris coolability
18 Mayo
Room-1.A.01
Modera
Sevostian Bechta
Pascal Piluso
-
Commissariat à l’énergie atomique et aux énergies alternatives, CEA, France
Development of the SAFARI Code for Comprehensive Severe Accident Analysis in Nuclear Reactors: Steam Explosion Analysis Module
Ju Bin Kim
Ph. D. Student
Seoul National University
EFFECT OF CORIUM PROPERTIES UNCERTAINTIES ON A PWR SBO SEVERE ACCIDENT
Luis Enrique Herranz
CIEMAT
CONSIDERATIONS ON FLOATING CRUSTS DURING MOLTEN CORE CONCRETE INTERACTION
Christophe Journeau
Tipo de sesión: Oral communications
Session 5.1 Hydrogen risk and Containment behavior
18 Mayo
Room-1.A.04
Modera
Mateusz Malicki
Scientist
Paul Scherrer Institut
Kevin Dieter
AMHYCO PROJECT OUTCOMES AND LESSONS LEARNED
Gonzalo Jimenez
CFD Analysis of the Containment Behavior during a TLAP Sequence in a Generic KWU PWR with containmentFOAM
Kelm Stephan
ETSON-AMHYCO BENCHMARK EXERCICE ON FLAME PROPAGATION IN REPRESENTATIVE REACTOR CONTAINMENT ATMOSPHERE IN CASE SEVERE ACCIDENT LATE PHASES
Ahmed Bentaib
Nuclear safety specialist
OECD-NEA
SUPPRESSION POOL MODELLING WITH THE CESAR THERMAL-HYDRAULIC MODULE OF ASTEC
Julie-Anne Zambaux
Engineer
ASNR
Tipo de sesión: Oral communications
Session 6.1 Source term
18 Mayo
Auditorio
Modera
Anne Cécile Gregoire
Teemu Kärkelä
Fission Product Pool Release Modeling in Modernized MELCOR: A Demonstration of Extensible Architecture and User-Defined Model Capabilities
David L. Luxat
Sandia National Laboratories
Severe Accident Source Term Analyses for VVER-1000 Focused on Iodine Speciation: Sensitivity Studies with Derived Best-Practices Using ASTEC/SOPHAEROS
Štěpán Tichý
Evaluation of the effect of different transport path modelling on FP behaviour in AC2/ATHLET-CD
Livia M.-Tiborcz
Technical Expert
Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH
Development of Evaluation Technology for Radiological Source Term in the Containment Using CINEMA Code During Severe Accidents
Donggun Son
Tipo de sesión: Oral communications
Session 3.2 Severe Accident Scenarios: Small Modular Reactors
18 Mayo
Auditorio
Modera
Mauricio Cazado
Research Scientist
Karlsruhe Institute of Technology
Stephan Brumm
Scientific Officer
European Commission JRC
SASPAM-SA WP5: Source Terme Estimation of Generic SMR Designs
Thorsten Hollands
Head of Containment Department
Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH
Gas phase iodine release from iPWR pool and dispersion in the atmosphere
Mateusz Malicki
Paul Scherrer Institute
MELCOR DEC-B Transient analysis in a generic integral Pressurized Water Reactor
Fabio Giannetti
Tipo de sesión: Oral communications
Session 7.1 Spent Fuel Pools
18 Mayo
Room-1.A.04
Modera
Anastasia Stakhanova
Wissenschaftlicher Mitarbeiterin
Karlsruhe Institute of Technology
Sandro Paci
University of Pisa
Recent Activities at Canadian Nuclear Laboratories on LOCA Progression in CANDU Spent Fuel Pools
Behnam Dastvareh
Validation of the Theoretical Approach for Modelling of the Hydride Morphology with Experimental Data for Zircaloy-4 obtained from SPIZWURZ bundle Test
Mikhail Kolesnik
Tipo de sesión: Oral communications
Session 1.2 Severe Accident Scenarios: Uncertainty and Sensitivity Analyses
19 Mayo
Auditorio
Modera
Livia M.-Tiborcz
Technical Expert
Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH
Fabio Giannetti
Employment of relative time scale in the U&S analysis of the MBLOCA scenario in a generic KONVOI NPP
Anastasia Stakhanova
Wissenschaftlicher Mitarbeiterin
Karlsruhe Institute of Technology
Calibration of the Postulated Scenario of Fukushima-Daiichi Unit 1 through the Application of Uncertainty Quantification
Luis E. Herranz
Head of the Unit of Nuclear Safety
CIEMAT
Integrated Severe Accident Analysis for a VVER-1000: Accident Progression, Uncertainty Quantification, and Radiological Consequences Assessment
Michela Angelucci
Tipo de sesión: Oral communications
Session 2.2 In-vessel Corium and debris coolability
19 Mayo
Room-1.A.04
Modera
Gaus-Liu Xiaoyang
Florian Fichot
Direct numerical evaluation of core equivalent conductivity: a comparative analysis of open rod and flat plate assemblies
LE TELLIER Romain
Experimental Investigation of Debris-Bed Formation for Optimizing Core-Catcher Design
Tomonari Mashiko
A comparison of EATF and Zircalloy-4 cladding behaviour under severe accident conditions from 1600°C till 1970°C in steam/argon atmosphere
Pascal Piluso
-
Commissariat à l’énergie atomique et aux énergies alternatives, CEA, France
Validation of Models on Corium Re-Melting and Melt Progression in Debris Beds based on LIVE L8 and LIVE J1 Experiments
Michael Buck
Head,Reactor Safety Division
Institute for Nuclear Technology and Energy Systems, University of Stuttgart
Tipo de sesión: Oral communications
Session 3.3 Severe Accident Scenarios: Small Modular Reactors
19 Mayo
Room-1.A.01
Modera
Fulvio Mascari
Senior Researcher
ENEA
Mateusz Malicki
Scientist
Paul Scherrer Institut
INVESTIGATION OF SEVERE ACCIDENT PROGRESSION IN INTEGRAL PWR SMRS
Govatsa Acharya
PhD Student
KTH Royal Institute of Technology
EVALUATION OF HYPOTHETICAL SEVERE ACCIDENT PROGRESSION WITH ATF CLADDING IN GENERIC INTEGRAL PWR DESIGNS IN THE FRAME OF THE SASPAM-SA PROJECT
Mauricio Cazado
Research Scientist
Karlsruhe Institute of Technology
Comparative Analysis of Containment Behavior in a Generic iPWR Design under Postulated BDBA Conditions Using ASTEC v3.1.2 and MELCOR v2.2 codes
Erik Cilia
ENEA
SASPAM-SA: Assessment of existing experimental data in WP3
Terttaliisa Lind
-
Paul Scherrer Institute, Switzerland
Tipo de sesión: Oral communications
Session 3.4 Severe Accident Scenarios: Small Modular Reactors
19 Mayo
Auditorio
Modera
Stephan Brumm
Scientific Officer
European Commission JRC
Federico Rocchi
Assessment of Emergency Planning Zone for iPWRs within the Horizon Euratom SASPAM-SA Project
Mikko Ilvonen
Senior Scientist
VTT Nuclear Energy, Finland
Performance Assessment of Passive Safety Systems and Identification of Conditions Leading to Design Extension Scenarios
Erik Cilia
ENEA
EFFECT OF DELAYED RECOVERY OF ECCS DURING SEVERE ACCIDENTS IN INTEGRAL PWR SMRS
Govatsa Acharya
PhD Student
KTH Royal Institute of Technology
Investigation of In Vessel Melt Retention by a stand-alone Lower Plenum ASTEC model of integral-PWR design#1 in the SASPAM-SA project
Stephan Brumm
Scientific Officer
European Commission JRC
Tipo de sesión: Oral communications
Session 5.2 Hydrogen risk and Containment behavior
19 Mayo
Room-1.A.04
Modera
Kelm Stephan
Gonzalo Jimenez
PARs for Hydrogen Measurement in Nuclear Containments in Severe Accidents
Lee Gardner
Development of a database for PAR model validation based on THAI experiments and its application in the framework of the AMHYCO project
Ernst-Arndt Reinecke
HYDROGEN RISK, FISSION PRODUCT BEHAVIOR AND SOURCE TERM IMPACTS IN EX-VESSEL PHASE USING THAI TEST DATA: THE OECD/NEA THEMIS PROJECT
Kevin Dieter
Development status of the flammability risk monitoring system in severe accidents
Youngsu Na
Tipo de sesión: Oral communications
Session 6.2 Source term
19 Mayo
Room-1.A.01
Modera
Terttaliisa Lind
-
Paul Scherrer Institute, Switzerland
Teemu Kärkelä
Developing a Concept for the Prediction of Long-Term Radionuclide Leaching from Corium in Post-Accident Scenarios
Florian Krist
Research Associate
Ruhr-Universität Bochum, Plant Simulation and Saftey
FissiOn pRoducts bEhavior under SeverE accident with New fuel concepts THE OECD/NEA FORESEEN PROJECT
Anne Cécile Gregoire
Scaling Effects in Iodine Retention for Filtered Containment Venting: Experimental Findings and Safety Implications
Sanjeev Gupta
-
Independent expert
A Deep Learning Surrogate Model for Rapid Prediction of Atmospheric Radioisotope Dispersion
Onur Murat
Research Scientist
Karlsruhe Institute of Technology
Tipo de sesión: Plenary Sessions
Plenary Session 2 – ‘EXPECTATIONS FROM SA R&D’
19 Mayo
Modera
Ahmed Bentaib
Nuclear safety specialist
OECD-NEA
Round table
Miguel Sánchez
Head of the Modeling and Simulation Area
Nuclear Safety Council (CSN)
Toyoshi Fuketa
Lourdes Borondo
Head of the Safety and Quality Unit
Cofrentes Nuclear Power Plant, operated by Iberdrola Generación Nuclear
Amparo Giner Gonzalez
OPERATION & TECHNICAL TRAINING MANAGER
Westinghouse Electric Company
Tipo de sesión: Oral communications
Session 1.3 Severe Accident Scenarios: Uncertainty and Sensitivity Analyses
19 Mayo
Auditorio
Modera
Michela Angelucci
Luis E. HERRANZ
Head of the Unit for Nuclear Safety Research
CIEMAT
Uncertainty quantification and sensitivity analysis of phenomenological uncertainty in the MAAP model for a severe accident loss of secondary heat sink
Claire Marshall
Severe Accident analysis in a generic iPWR and uncertainty quantification of the results
Fulvio Mascari
Senior Researcher
ENEA
Stepwise Uncertainty Analysis Methodology: First insights
Rafael Bocanegra Melian
Senior Engineer
ENSO
Tipo de sesión: Oral communications
Session 2.3 In-vessel Corium and debris coolability
19 Mayo
Room-1.A.04
Modera
Mauricio Cazado
Research Scientist
Karlsruhe Institute of Technology
Mateusz Malicki
Scientist
Paul Scherrer Institut
W-STORM sensitivity and uncertainty analysis for In Vessel Retention in integral Pressurized Water Reactors
Principato Marcello
PhD student
Sapienza University of Rome
Experimental Study on the Naturally Stratified Melt Pool Based on High-Temperature Chloride Salts and Mg–Al Alloys
Fengyang QUAN
Senior Engineer
China Nuclear Power Engineering CO., LTD
Stand-alone analysis and evaluation of uncertainties of IVMR in SMR using AC2 code
Mindaugas Valinčius
Senior Research Associate
Lithuanian Energy Institute
Tipo de sesión: Oral communications
Session 4.2 Ex-vessel Corium and debris coolability
19 Mayo
Room-1.A.01
Modera
Fabio Giannetti
Christophe Journeau
Geometrical prerequisites for ex-vessel recriticality in flooded cavity containments
Björn Engström
Performance of innovative sacrificial materials for PWR retrofitting - a reactor case study
Petr Vácha
Head of Severe Accidents Department
UJV Rez, a.s.
Development of the SAFARI Code for Comprehensive Severe Accident Analysis in Nuclear Reactors: Molten Corium-Concrete Interaction Analysis Module
JUN SUNG CHOI
PhD candidate
Seoul National University
Tipo de sesión: Plenary Sessions
Plenary Session 3 – R&D INTERNATIONAL FRAMEWORKS: NEW PROJECT PLATFORMS AND DATA BASES FOR SA
20 Mayo
Modera
Federico Rocchi
Euratom Research activities on Severe Accidents
Angelgiorgo Iorizzo
PO
European Commission, RTD, Euratom Research
Recent IAEA Activities Related to Severe Accidents
Alexei Miassoedov
Nuclear Engineer working on advanced water-cooled reactors
International Atomic Energy Agency
Enabling Nuclear Safety Research: NEA Frameworks and Databases
Martina Adorni
Nuclear Safety Specialist
Nuclear Energy Agency, France
Tipo de sesión: Oral communications
Session 1.4 Severe Accident Scenarios
20 Mayo
Room-1.A.04
Modera
Laure Carenini
-
Autorité de sûreté nucléaire et de radioprotection, France
Matthias Braun
Integral Phenomena Identification and Ranking Table on Severe Accidents: Methodology and Major Outcomes
Luis Enrique Herranz
Head of the Unit of Nuclear Safety Research
CIEMAT
More than two decades of activities on Severe Accident Management Guidelines (SAMG) in Tacnatom and Westinghouse
Agustin Tanarro Onrubia
Principal Engineer
Westinghouse
Simulating the asymmetrical behavior of TMI-2 accident with AC2/ATHLET-CD
Liviusz Lovasz
Chief Expert for Core Degradation
GRS
ASSAS Simulator for Severe Accident analysis for educational purposes
MARIANO MARTIN GARCIA
Tipo de sesión: Oral communications
Session 2.4 In-vessel Corium and debris coolability
20 Mayo
Auditorio
Modera
Nathalie SEILER
Alexei Miassoedov
Nuclear Engineer working on advanced water-cooled reactors
International Atomic Energy Agency
A path forward to improve corium thermodynamic assessment by using surface tension data: results for the U-O binary system
LE TELLIER Romain
Estimation of the cooling rate of U-Zr-Fe-Cr-O sample which underwent melting
Yoichi Endo
Critical Heat Flux in Pool boiling configuration for In-Vessel Melt Retention: literature review and recents experiments in THS-15 facility
AT KHEN Kresna
BWR RPV Lower Head Penetration Failure Caused by Eutectic Reactions with Zr-Rich Simulated Metal: ELSA-3 Test
KENTA SHIMOMURA
Researcher
Japan Atomic Energy Agency
Investigation on In-Vessel Phase of BDB-LOCA of Supercritical Water-cooled Fast Reactor
Yuma Kobayashi
Graduate Student
Graduate School of Advanced Science and Engineering Waseda University
Tipo de sesión: Oral communications
Session 4.3 Ex-vessel Corium and debris coolability
20 Mayo
Room-1.A.01
Modera
Sevostian Bechta
Christophe Journeau
Merging NUCLEA and Mephista databases: Over three decades of building a European Nuclear Thermodynamic Database for severe accident phenomenology.
Bénédicte MICHEL
Research engineer
ASNR
Simulation of Melt Debris Spreading Behavior in a Core Catcher Using THERMOS
Wataru Kikuchi
Researcher
Nuclear Regulation Authority, JAPAN
Experimental Study on the Interaction Between Molten Corium Simulant and Sacrificial Materials
Nan Li
Beijing,China
China Nuclear Power Engineering Co., Ltd
Advancing the Jet Breakup Length Model for Fuel-Coolant Interaction in Light Water Reactors
Kwang-Hyun Bang
Numerical Simulation of Melt Dry Spreading in CoSMUS Experiments
Lu Zhao
Tipo de sesión: Oral communications
Session 4.4 Ex-vessel Corium and debris coolability
20 Mayo
Room-1.A.01
Modera
Pascal Piluso
-
Commissariat à l’énergie atomique et aux énergies alternatives, CEA, France
Gaus-Liu Xiaoyang
Further development of a machine learning model for predicting the long-term coolability of debris beds
Nicole Richter
Research assistant
Ruhr-Universität Bochum, Plant Simulation and Safety Group (PSS)
AI-Driven Estimation of Corium Thermophysical Properties for Ex-Vessel Corium Stabilization Simulations
Raphaël MONOD
Investigation on the Melt Transport Behavior in the Drywell of Fukushima Daiichi Nuclear Power Plant Unit-1 with MPS Method
Xin Li
An advanced graph neural network application to highly viscous newtonian fluid flow towards the rapid corium spreading simulation
Hiroki Asatsuma
Student
The University of Tokyo
Tipo de sesión: Oral communications
Session 5.3 Hydrogen risk and Containment behavior
20 Mayo
Auditorio
Modera
Gonzalo Jimenez
Ernst-Arndt Reinecke
Department Head
Forschungszentrum Juelich GmbH
Influence of Containment Pressurization Rates on the Assessment of Severe Accident Risk
Kwang-Il Ahn
BENCHMARK ON COUNTER-CURRENT FLOW IN MULTI-COMPARTMENT CONTAINMENT USING THAI TEST DATA
Jens Hermann
Systematic analysis of the influence of the spray actuation on the hydrogen risk using a 3D GOTHIC PWR-W model
Carlos Vázquez-Rodríguez
Assessment and Applicability of a Stand-Alone Containment Methodology for Hydrogen and CO Risk Evaluation in Severe Accidents
Joan Fontanet
Tipo de sesión: Oral communications
Session 6.3 Source term
20 Mayo
Room-1.A.04
Modera
Anne Cécile Gregoire
Experimental Investigation on Effect of Obstacle Structure on Aerosol Deposition at Different Generation Rates in the Context of Decommissioning of Fukushima Daiichi Nuclear Power Plant
Ruicong XU
Chemistry of Chromium in the Reactor Coolant System in severe accident conditions from an ATF type core
Bouchain Joâo
Interfacial gas transfer in gas-liquid flows: a comparative study of advanced experimental and computational techniques
Alvaro Ramos Perez
PhD student
PSI
IMPACT OF ASTEC’S ADVANCED MODELING IN GAS AND ADSORBED PHASES CHEMISTRY ON THE SOURCE TERM
Sidi M. O. Souvi
Researcher
ASNR
Tipo de sesión: Oral communications
Session 1.5: Severe Accident Scenarios: Integral Codes and Research Frameworks
20 Mayo
Auditorio
Modera
Joan Fontanet
Liviusz Lovasz
Chief Expert for Core Degradation
GRS
MELCOR Code Modernization: A Generalized Architecture for Advanced Severe Accident Phenomenology
David L. Luxat
Sandia National Laboratories
CNL SEVERE ACCIDENT ANALYSIS RESEARCH TO SUPPORT SAFE DEPLOYMENT OF SMALL MODULAR AND ADVANCED REACTORS
Andrew Morreale
Technical Manager - Reactor Safety
Canadian Nuclear Laboratories (CNL)
Development of the SAFARI Code for Comprehensive Severe Accident Analysis in Nuclear Reactors: Containment Thermal-Hydraulics Analysis Module
KumHo Han
Associate Manager
FNC Technology
Tipo de sesión: Oral communications
Session 5.4 Hydrogen risk and Containment behavior
20 Mayo
Room-1.A.01
Modera
Sanjeev Gupta
-
Independent expert
Kevin Dieter
EX-VESSEL SEVERE ACCIDENT 3D SIMULATION WITH GOTHIC 8.3(QA): METHODOLOGY AND APPLICATION TO A PWR-KWU CONTAINMENT
LUIS SERRA LOPEZ
IMPLEMENTATION OF A SAFETY-RELATED AIR-COOLING SYSTEM IN A PWR-W DRY CONTAINMENT USING GOTHIC 3D
Alberto García-Herranz
Pre-doctoral Researcher
Universidad Politécnica de Madrid (UPM)
Passive Autocatalytic Recombination of Hydrogen – An Application in the ITER Fusion Reactor
Matthias Braun
Tipo de sesión: Oral communications
Session 6.4 Source term
20 Mayo
Room-1.A.04
Modera
Ahmed BENTAIB
Senior researcher
ASNR
Ivo Kljenak
Scientific councillor
Jozef Stefan Institute
Assessment of pool scrubbing predictive capabilities: benchmarking SPARC90 against an ad-hoc database
Giacomo Tinfena
POOL SCRUBBING IN WATER COOLED SMRs: SCENARIOS, PECULIARITIES AND CHALLENGES
Luis E. HERRANZ
Head of the Unit for Nuclear Safety Research
CIEMAT
MAAP6 Mechanistic Pool Scrubbing Model
Paul McMinn
Lead Engineer
Westinghouse
COCOSYS simulation of CsI decomposition under irradiation and the formation of organic iodide in the containment
Optimising Electrostatic Precipitators for Severe Accident Scenarios: Impact of Key Operational Parameters
Satish Basnet
Overview of Fission Product Behavior Modeling in the SIRIUS Code
JAEHYUN HAM
Advanced Modeling of Fission Product Release from Irradiated Fuel during Severe Accident Scenarios
Giacomo Petrosillo
PhD Student
CEA
Tipo de sesión: Oral communications
Session 7.2 Generation IV Systems: Sodium Fast Reactors
21 Mayo
Room-1.A.04
Modera
Nathalie SEILER
Alexei Miassoedov
Nuclear Engineer working on advanced water-cooled reactors
International Atomic Energy Agency
Validation of Species Transport Modeling in Liquid Sodium Systems: Extension of SPARC-90/University of Wisconsin-Madison Benchmarks to Modernized MELCOR
David L. Luxat
Sandia National Laboratories
Experimental validation of the core catcher safety measures in Gen IV ESFR conceptual design against long-term ablation
Gaus-Liu Xiaoyang
Investigation of film boiling in liquid sodium: the SERUA experimental program
Clavier Rémi
Benchmarking of Advanced GPU-Accelerated Discrete Element Method and Elastoplastic Constitutive Granular Flow Models for Large-Scale Debris Bed Formation in Severe Accidents of Sodium Fast Reactors
Ryo Yokoyama
Tipo de sesión: Oral communications
Session 7.3 Advanced Technological Fuels and Materials
21 Mayo
Room-1.A.01
Modera
Mauricio Cazado
Research Scientist
Karlsruhe Institute of Technology
Livia M.-Tiborcz
Technical Expert
Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH
Cr-coated claddings modelling in the severe accident code ASTEC
Laure Carenini
-
Autorité de sûreté nucléaire et de radioprotection, France
Development and Validation of the FeCrAl oxidation model of the ASTEC integral code based on the QUENCH Experimental Results
Zaira Itzel Jiménez Balbuena
Student
Karlsruhe Institute of Technology
The integral air ingress CODEX-ATF-AIT experiment
Róbert Farkas
Comparative Analyses of Creep Models for Predicting Behavior of RPV Steel under Extreme High Temperatures
xiangyu li
Tipo de sesión: Oral communications
Session 4.5 Ex-vessel Corium and debris coolability
21 Mayo
Auditorio
Modera
Pascal Piluso
-
Commissariat à l’énergie atomique et aux énergies alternatives, CEA, France
Thorsten Hollands
Head of Containment Department
Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH
Development of the SAFARI Code for Comprehensive Severe Accident Analysis in Nuclear Reactors: Corium–Coolant Interaction Analysis Module
Minchan Kwon
Ph. D. Student
Seoul National University
Evaluation of concrete ablation by a hot heat-generating solid
Alejandro VILLARREAL LARRAURI
Modelling of Molten Corium Jet Impingement
Michael Buck
Head,Reactor Safety Division
Institute for Nuclear Technology and Energy Systems, University of Stuttgart
Tipo de sesión: Oral communications
Session 7.4 Generation IV Systems
21 Mayo
Room-1.A.04
Modera
Anastasia Stakhanova
Wissenschaftlicher Mitarbeiterin
Karlsruhe Institute of Technology
Sanjeev Gupta
-
Independent expert
High temperature oxidation behavior of silicon carbide fuel matrix during Beyond Design Basis Accident in Gen Ⅳ reactors
Yosuke NISHIMURA
MSR Modeling Capabilities and Development with the MELCOR Reactor Simulation
David L. Luxat
Sandia National Laboratories
Computational verification of the functionality of the cooling system of the ALLEGRO reactor core catcher
Jan Komrska
Researcher, PhD Student
Czech Technical University - Faculty of Mechanical Engineering
Tipo de sesión: ADDITIONAL INFORMATION
Group Photo
21 Mayo
Tipo de sesión: Plenary Sessions
Closing Plenary Session
21 Mayo
Modera
Sandro Paci
University of Pisa
Ahmed BENTAIB
Senior researcher
ASNR
ERMSAR2026 in numbers
Fabrizio Gabrielli
Deputy Group Leader
Karlsruhe Institute of Technology
Concluding Remarks
Luis E. HERRANZ
Head of the Unit for Nuclear Safety Research
CIEMAT
Introduction of ERMSAR2028
Ivo Kljenak
Scientific councillor
Jozef Stefan Institute
Tipo de sesión: ADDITIONAL INFORMATION
Meeting point: Av. Complutense 40, Madrid. Participants are responsible for their own travel to the CIEMAT premises.
22 Mayo
Laboratories and facilities at CIEMAT’s headquarters
Tipo de sesión: Technical Visit
Access procedures
22 Mayo
Laboratories and facilities at CIEMAT’s headquarters
Tipo de sesión: ADDITIONAL INFORMATION
MEETING ERMSAR VENUE 8:45
22 Mayo
Simulators at Westinghouse facilities - BUS 1
Tipo de sesión: Technical Visit
Bus departure
22 Mayo
Simulators at Westinghouse facilities - BUS 1
Tipo de sesión: Technical Visit
Fusion facilities
22 Mayo
Laboratories and facilities at CIEMAT’s headquarters
Grooup I: Stellarator TJ-II
Group II: Liquid metals laboratory
Grupo swap
Visit exchange
Tipo de sesión: ADDITIONAL INFORMATION
MEETING ERMSAR VENUE 9:15
22 Mayo
Simulators at Westinghouse facilities - BUS 2
Tipo de sesión: Technical Visit
Bus departure
22 Mayo
Simulators at Westinghouse facilities - BUS 2
Tipo de sesión: Technical Visit
Arrival to Westinghouse premises
22 Mayo
Simulators at Westinghouse facilities - BUS 1
Tipo de sesión: Technical Visit
Severe accident simulator (ASSAS) (*)
22 Mayo
Simulators at Westinghouse facilities - BUS 1
Tipo de sesión: Technical Visit
Coffee break
22 Mayo
Laboratories and facilities at CIEMAT’s headquarters
Tipo de sesión: Technical Visit
Arrival to Westinghouse premises
22 Mayo
Simulators at Westinghouse facilities - BUS 2
Tipo de sesión: Technical Visit
Severe accident simulator (ASSAS) (*)
22 Mayo
Simulators at Westinghouse facilities - BUS 2
Tipo de sesión: Technical Visit
AP1000 simulator(*)
22 Mayo
Simulators at Westinghouse facilities - BUS 1
Tipo de sesión: Technical Visit
Facilities of the Material Department
22 Mayo
Laboratories and facilities at CIEMAT’s headquarters
Group I: IR-09
Group II: Corrosion laboratory
Visit exchange
Transfer to facilities of Fission Dep.
Tipo de sesión: Technical Visit
AP1000 simulator (*)
22 Mayo
Simulators at Westinghouse facilities - BUS 2
Tipo de sesión: Technical Visit
PWR-KWU simulator (*)
22 Mayo
Simulators at Westinghouse facilities - BUS 1
Tipo de sesión: Technical Visit
Facilities of the Fission Department
22 Mayo
Laboratories and facilities at CIEMAT’s headquarters
Group I: Nuclear data laboratory
Group II: Neutron standard laboratory
Group Swap
Visit exchange
Tipo de sesión: Technical Visit
PWR-KWU simulator (*)
22 Mayo
Simulators at Westinghouse facilities - BUS 2
Tipo de sesión: Technical Visit
Bus departure to Madrid
22 Mayo
Simulators at Westinghouse facilities - BUS 1
Tipo de sesión: Technical Visit
Bus departure to Madrid
22 Mayo
Simulators at Westinghouse facilities - BUS 2
Tipo de sesión: Technical Visit
Arrival to ERMSAR venue
22 Mayo
Simulators at Westinghouse facilities - BUS 1
Tipo de sesión: Technical Visit
Arrival to ERMSAR venue
22 Mayo
Simulators at Westinghouse facilities - BUS 2
Tipo de sesión: ADDITIONAL INFORMATION
(*) The order of simulator visits may change due to availability and organizational concerns at Westinghouse
22 Mayo
Simulators at Westinghouse facilities - BUS 1
Tipo de sesión: ADDITIONAL INFORMATION
(*) The order of simulator visits may change due to availability and organizational concerns at Westinghouse
22 Mayo
Simulators at Westinghouse facilities - BUS 2
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