18 May
19 May
20 May
21 May
22 May
Filter
08:00 - 08:05
UPLOAD E-POSTERS
08:20 - 09:00
Registration
09:00 - 09:45
Welcome and opening
09:45 - 10:45
Plenary Session 1 – SINGULAR CAREERS IN THE SEVERE ACCIDENT RESEARCH
10:45 - 11:10
Coffee break
11:10 - 13:00
Session 1.1 Severe Accident Scenarios
11:10 - 13:00
Session 2.1 In-vessel Corium and debris coolability
11:10 - 13:00
Session 3.1 Severe Accident Scenarios: Small Modular Reactors
13:00 - 14:00
Lunch
14:00 - 16:10
Session 4.1 Ex-vessel Corium and debris coolability
14:00 - 16:10
Session 5.1 Hydrogen risk and Containment behavior
14:00 - 16:10
Session 6.1 Source term
15:40 - 16:00
Coffee break
16:00 - 17:15
Session 7.1 Spent Fuel Pools
16:10 - 17:15
Session 3.2 Severe Accident Scenarios: Small Modular Reactors
09:00 - 10:40
Session 1.2 Severe Accident Scenarios: Uncertainty and Sensitivity Analyses
09:00 - 10:40
Session 2.2 In-vessel Corium and debris coolability
09:00 - 10:40
Session 3.3 Severe Accident Scenarios: Small Modular Reactors
10:40 - 11:10
Coffee break
11:10 - 13:00
Session 3.4 Severe Accident Scenarios: Small Modular Reactors
11:10 - 13:00
Session 5.2 Hydrogen risk and Containment behavior
11:10 - 13:00
Session 6.2 Source term
13:00 - 14:00
Lunch
14:00 - 15:30
Plenary Session 2 – ‘EXPECTATIONS FROM SA R&D’
15:30 - 16:30
Coffee break and poster session
16:30 - 17:45
Session 1.3 Severe Accident Scenarios: Uncertainty and Sensitivity Analyses
16:30 - 17:45
Session 2.3 In-vessel Corium and debris coolability
16:30 - 17:45
Session 4.2 Ex-vessel Corium and debris coolability
19:30 - 20:30
Flamenco show (if you select the corresponding fee)
09:00 - 10:30
Plenary Session 3 – Research and Developement Frameworks
10:30 - 10:50
Coffee break and poster session
10:50 - 13:00
Session 1.4 Severe Accident Scenarios
10:50 - 13:00
Session 2.4 In-vessel Corium and debris coolability
10:50 - 13:00
Session 4.3 Ex-vessel Corium and debris coolability
13:00 - 14:00
Lunch
14:00 - 16:10
Session 4.4 Ex-vessel Corium and debris coolability
14:00 - 16:10
Session 5.3 Hydrogen risk and Containment behavior
14:00 - 16:10
Session 6.3 Source term
15:40 - 16:00
Coffee break and poster session
16:00 - 17:45
Session 1.5: Severe Accident Scenarios: Integral Codes and Research Frameworks
16:00 - 17:45
Session 5.4 Hydrogen risk and Containment behavior
16:00 - 17:45
Session 6.4 Source term
20:00 - 20:30
Cocktail (Spanish wine)
20:30 - 22:00
Dinner
09:00 - 10:40
Session 6.5 Source Term
09:00 - 10:40
Session 7.2 Generation IV Systems: Sodium Fast Reactors
09:00 - 10:40
Session 7.3 Advanced Technological Fuels and Materials
10:40 - 10:55
Coffee break and poster session
10:55 - 12:20
Session 4.5 Ex-vessel Corium and debris coolability
10:55 - 12:20
Session 7.4 Generation IV Systems
12:20 - 12:35
Group Photo
12:35 - 13:15
Closing Plenary Session
13:15 - 14:15
Lunch and poster session
15:00 - 17:00
NUGENIA TA2 Meeting (Restricted)
08:00 - 08:40
Meeting point: Av. Complutense 40, Madrid. Participants are responsible for their own travel to the CIEMAT premises.
08:40 - 09:00
Access procedures
08:45 - 09:00
MEETING ERMSAR VENUE 8:45
09:00 - 09:00
Bus Departure
09:00 - 10:10
Fusion facilities
09:15 - 09:30
MEETING ERMSAR VENUE 9:15
09:30 - 10:15
Bus departure
09:45 - 10:00
Arrival to Westinghouse premises
10:00 - 10:35
Severe accident simulator (ASSAS) (*)
10:10 - 10:50
Coffee break
10:15 - 10:30
Arrival to Westinghouse premises
10:30 - 11:05
Severe accident simulator (ASSAS) (*)
10:35 - 11:10
AP1000 simulator(*)
10:50 - 11:30
Facilities of the Material Department
11:05 - 11:40
AP1000 simulator (*)
11:10 - 11:50
PWR-KWU simulator (*)
11:20 - 12:10
Facilities of the Fission Department
11:40 - 12:20
PWR-KWU simulator (*)
11:50 - 12:35
Bus departure to Madrid
12:10 - 12:10
END of the visit
12:20 - 13:05
Bus departure to Madrid
12:35 - 12:40
Arrival to ERMSAR venue
13:05 - 13:10
Arrival to ERMSAR venue
14:00 - 14:00
(*) The order of simulator visits may change due to availability and organizational concerns at Westinghouse
14:00 - 14:00
(*) The order of simulator visits may change due to availability and organizational concerns at Westinghouse
Session type: Welcome
Registration
18 May
8:20 - 9:00
Session type: Welcome
Welcome and opening
18 May
9:00 - 9:45
Moderate
Sandro Paci
Pisa University
Fabrizio Gabrielli
Karlsruhe Institute of Technology
.
Félix Barrio
CIEMAT
Santiago Aleza Enciso
CSN
Luis E. HERRANZ
CIEMAT
Session type: Plenary Sessions
Plenary Session 1 – SINGULAR CAREERS IN THE SEVERE ACCIDENT RESEARCH
18 May
9:45 - 10:45
Moderate
Terttaliisa Lind
Paul Scherrer Institute, Switzerland
30 years of materials science for nuclear safety. From unexpected findings to improved severe accident codes
Martin Steinbrück
Karlsruhe Institute of Technology (KIT)
Research, Insights, and Lessons Learned During a Career Focused on Ex-Vessel Severe Accident Behavior
Mitchell Farmer
Nuclear Science and Engineering Division, Argonne National Laboratory
Session type: Oral communications
Session 1.1 Severe Accident Scenarios
18 May
Room-1.A.01
11:10 - 13:00
Moderate
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
Session type: Oral communications
Session 2.1 In-vessel Corium and debris coolability
18 May
Room-1.A.04
11:10 - 13:00
Moderate
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
Session type: Oral communications
Session 3.1 Severe Accident Scenarios: Small Modular Reactors
18 May
Auditorio
11:10 - 13:00
Moderate
MÓNICA GARCÍA MARTÍN
CIEMAT
Fulvio Mascari
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
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
Session type: Oral communications
Session 4.1 Ex-vessel Corium and debris coolability
18 May
Room-1.A.01
14:00 - 16:10
Moderate
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
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
Session type: Oral communications
Session 5.1 Hydrogen risk and Containment behavior
18 May
Room-1.A.04
14:00 - 16:10
Moderate
Mateusz Malicki
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
OECD-NEA
SUPPRESSION POOL MODELLING WITH THE CESAR THERMAL-HYDRAULIC MODULE OF ASTEC
Julie-Anne Zambaux
ASNR
Session type: Oral communications
Session 6.1 Source term
18 May
Auditorio
14:00 - 16:10
Moderate
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
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
Session type: Oral communications
Session 7.1 Spent Fuel Pools
18 May
Room-1.A.04
16:00 - 17:15
Moderate
Anastasia Stakhanova
Karlsruhe Institute of Technology
Sandro Paci
Pisa University
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
Session type: Oral communications
Session 3.2 Severe Accident Scenarios: Small Modular Reactors
18 May
Auditorio
16:10 - 17:15
Moderate
Mauricio Cazado
Karlsruhe Institute of Technology
Stephan Brumm
European Commission JRC
SASPAM-SA WP5: Source Terme Estimation of Generic SMR Designs
Thorsten Hollands
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
Session type: Oral communications
Session 1.2 Severe Accident Scenarios: Uncertainty and Sensitivity Analyses
19 May
Auditorio
9:00 - 10:40
Moderate
Livia M.-Tiborcz
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
Karlsruhe Institute of Technology
Calibration of the Postulated Scenario of Fukushima-Daiichi Unit 1 through the Application of Uncertainty Quantification
Luis E. Herranz
CIEMAT
Integrated Severe Accident Analysis for a VVER-1000: Accident Progression, Uncertainty Quantification, and Radiological Consequences Assessment
Michela Angelucci
Session type: Oral communications
Session 2.2 In-vessel Corium and debris coolability
19 May
Room-1.A.04
9:00 - 10:40
Moderate
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
Institute for Nuclear Technology and Energy Systems, University of Stuttgart
Session type: Oral communications
Session 3.3 Severe Accident Scenarios: Small Modular Reactors
19 May
Room-1.A.01
9:00 - 10:40
Moderate
Fulvio Mascari
ENEA
Mateusz Malicki
Paul Scherrer Institut
INVESTIGATION OF SEVERE ACCIDENT PROGRESSION IN INTEGRAL PWR SMRS
Govatsa Acharya
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
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
University of Bologna
SASPAM-SA: Assessment of existing experimental data in WP3
Terttaliisa Lind
Paul Scherrer Institute, Switzerland
Session type: Oral communications
Session 3.4 Severe Accident Scenarios: Small Modular Reactors
19 May
Auditorio
11:10 - 13:00
Moderate
Stephan Brumm
European Commission JRC
Federico Rocchi
Assessment of Emergency Planning Zone for iPWRs within the Horizon Euratom SASPAM-SA Project
Mikko Ilvonen
VTT Nuclear Energy, Finland
Performance Assessment of Passive Safety Systems and Identification of Conditions Leading to Design Extension Scenarios
Erik Cilia
University of Bologna
EFFECT OF DELAYED RECOVERY OF ECCS DURING SEVERE ACCIDENTS IN INTEGRAL PWR SMRS
Govatsa Acharya
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
European Commission JRC
Session type: Oral communications
Session 5.2 Hydrogen risk and Containment behavior
19 May
Room-1.A.04
11:10 - 13:00
Moderate
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
Session type: Oral communications
Session 6.2 Source term
19 May
Room-1.A.01
11:10 - 13:00
Moderate
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
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
Karlsruhe Institute of Technology
Session type: Plenary Sessions
Plenary Session 2 – ‘EXPECTATIONS FROM SA R&D’
19 May
14:00 - 15:30
Moderate
Ahmed Bentaib
OECD-NEA
Round table
Miguel Sánchez
Nuclear Safety Council (CSN)
Toyoshi Fuketa
Lourdes Borondo
Cofrentes Nuclear Power Plant, operated by Iberdrola Generación Nuclear
Amparo Giner Gonzalez
Westinghouse Electric Company
Session type: Oral communications
Session 1.3 Severe Accident Scenarios: Uncertainty and Sensitivity Analyses
19 May
Auditorio
16:30 - 17:45
Moderate
Michela Angelucci
Luis E. HERRANZ
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
ENEA
Stepwise Uncertainty Analysis Methodology: First insights
Rafael Bocanegra Melian
ENSO
Session type: Oral communications
Session 2.3 In-vessel Corium and debris coolability
19 May
Room-1.A.04
16:30 - 17:45
Moderate
Mauricio Cazado
Karlsruhe Institute of Technology
Mateusz Malicki
Paul Scherrer Institut
W-STORM sensitivity and uncertainty analysis for In Vessel Retention in integral Pressurized Water Reactors
Principato Marcello
Sapienza University of Rome
Experimental Study on the Naturally Stratified Melt Pool Based on High-Temperature Chloride Salts and Mg–Al Alloys
Fengyang QUAN
China Nuclear Power Engineering CO., LTD
Stand-alone analysis and evaluation of uncertainties of IVMR in SMR using AC2 code
Mindaugas Valinčius
Lithuanian Energy Institute
Session type: Oral communications
Session 4.2 Ex-vessel Corium and debris coolability
19 May
Room-1.A.01
16:30 - 17:45
Moderate
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
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
Seoul National University
Session type: Plenary Sessions
Plenary Session 3 – Research and Developement Frameworks
20 May
9:00 - 10:30
Moderate
Federico Rocchi
Speakers
Angelgiorgo Iorizzo
European Commission, RTD, Euratom Research
Recent IAEA Activities Related to Severe Accidents
Alexei Miassoedov
IAEA
Enabling Nuclear Safety Research: NEA Frameworks and Databases
Martina Adorni
Nuclear Energy Agency, France
Session type: Oral communications
Session 1.4 Severe Accident Scenarios
20 May
Room-1.A.04
10:50 - 13:00
Moderate
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
CIEMAT
More than two decades of activities on Severe Accident Management Guidelines (SAMG) in Tacnatom and Westinghouse
Agustin Tanarro Onrubia
Westinghouse
Simulating the asymmetrical behavior of TMI-2 accident with AC2/ATHLET-CD
Liviusz Lovasz
GRS
ASSAS Simulator for Severe Accident analysis for educational purposes
MARIANO MARTIN GARCIA
Session type: Oral communications
Session 2.4 In-vessel Corium and debris coolability
20 May
Auditorio
10:50 - 13:00
Moderate
Nathalie SEILER
Alexei Miassoedov
IAEA
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
Japan Atomic Energy Agency
Investigation on In-Vessel Phase of BDB-LOCA of Supercritical Water-cooled Fast Reactor
Yuma Kobayashi
Graduate School of Advanced Science and Engineering Waseda University
Session type: Oral communications
Session 4.3 Ex-vessel Corium and debris coolability
20 May
Room-1.A.01
10:50 - 13:00
Moderate
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
ASNR
Simulation of Melt Debris Spreading Behavior in a Core Catcher Using THERMOS
Wataru Kikuchi
Nuclear Regulation Authority, JAPAN
Experimental Study on the Interaction Between Molten Corium Simulant and Sacrificial Materials
Nan Li
CNNC Key Laboratory for Severe Accident Research in Nuclear Power Safety, 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
Session type: Oral communications
Session 4.4 Ex-vessel Corium and debris coolability
20 May
Room-1.A.01
14:00 - 16:10
Moderate
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
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
The University of Tokyo
Session type: Oral communications
Session 5.3 Hydrogen risk and Containment behavior
20 May
Auditorio
14:00 - 16:10
Moderate
Gonzalo Jimenez
Ernst-Arndt Reinecke
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
Session type: Oral communications
Session 6.3 Source term
20 May
Room-1.A.04
14:00 - 16:10
Moderate
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
PSI
IMPACT OF ASTEC’S ADVANCED MODELING IN GAS AND ADSORBED PHASES CHEMISTRY ON THE SOURCE TERM
Sidi M. O. Souvi
ASNR
Session type: Oral communications
Session 1.5: Severe Accident Scenarios: Integral Codes and Research Frameworks
20 May
Auditorio
16:00 - 17:45
Moderate
Joan Fontanet
Liviusz Lovasz
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
Canadian Nuclear Laboratories (CNL)
Development of the SAFARI Code for Comprehensive Severe Accident Analysis in Nuclear Reactors: Containment Thermal-Hydraulics Analysis Module
KumHo Han
FNC Technology
Session type: Oral communications
Session 5.4 Hydrogen risk and Containment behavior
20 May
Room-1.A.01
16:00 - 17:45
Moderate
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
Universidad Politécnica de Madrid (UPM)
Passive Autocatalytic Recombination of Hydrogen – An Application in the ITER Fusion Reactor
Matthias Braun
Session type: Oral communications
Session 6.4 Source term
20 May
Room-1.A.04
16:00 - 17:45
Moderate
Ahmed BENTAIB
ASNR
Ivo Kljenak
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
CIEMAT
MAAP6 Mechanistic Pool Scrubbing Model
Paul McMinn
Westinghouse
COCOSYS simulation of CsI decomposition under irradiation and the formation of organic iodide in the containment
Chuanhe Lu
Session type: Oral communications
Session 6.5 Source Term
21 May
Auditorio
9:00 - 10:40
Moderate
Kelm Stephan
Ivo Kljenak
Jozef Stefan Institute
Factors influencing radiation-induced Corium matrix dissolution
Helena Aubets
KTH Royal Institute of Technology
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
CEA
Session type: Oral communications
Session 7.2 Generation IV Systems: Sodium Fast Reactors
21 May
Room-1.A.04
9:00 - 10:40
Moderate
Nathalie SEILER
Alexei Miassoedov
IAEA
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
Session type: Oral communications
Session 7.3 Advanced Technological Fuels and Materials
21 May
Room-1.A.01
9:00 - 10:40
Moderate
Mauricio Cazado
Karlsruhe Institute of Technology
Livia M.-Tiborcz
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
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
Session type: Oral communications
Session 4.5 Ex-vessel Corium and debris coolability
21 May
Auditorio
10:55 - 12:20
Moderate
Pascal Piluso
Commissariat à l’énergie atomique et aux énergies alternatives, CEA, France
Thorsten Hollands
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
Seoul National University
Evaluation of concrete ablation by a hot heat-generating solid
Alejandro VILLARREAL LARRAURI
Modelling of Molten Corium Jet Impingement
Michael Buck
Institute for Nuclear Technology and Energy Systems, University of Stuttgart
Session type: Oral communications
Session 7.4 Generation IV Systems
21 May
Room-1.A.04
10:55 - 12:20
Moderate
Anastasia Stakhanova
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
Czech Technical University - Faculty of Mechanical Engineering
Session type: ADDITIONAL INFORMATION
Group Photo
21 May
12:20 - 12:35
Session type: Plenary Sessions
Closing Plenary Session
21 May
12:35 - 13:15
Moderate
Sandro Paci
Pisa University
Ahmed BENTAIB
ASNR
ERMSAR2026 in numbers
Fabrizio Gabrielli
Karlsruhe Institute of Technology
Concluding Remarks
Luis E. HERRANZ
CIEMAT
Introduction of ERMSAR2028
Ivo Kljenak
Jozef Stefan Institute
Session type: ADDITIONAL INFORMATION
Meeting point: Av. Complutense 40, Madrid. Participants are responsible for their own travel to the CIEMAT premises.
22 May
Laboratories and facilities at CIEMAT’s headquarters
8:00 - 8:40
Session type: Technical Visit
Access procedures
22 May
Laboratories and facilities at CIEMAT’s headquarters
8:40 - 9:00
Session type: ADDITIONAL INFORMATION
MEETING ERMSAR VENUE 8:45
22 May
Simulators at Westinghouse facilities - BUS 1
8:45 - 9:00
Session type: Technical Visit
Bus Departure
22 May
Simulators at Westinghouse facilities - BUS 1
9:00 - 9:00
Session type: Technical Visit
Fusion facilities
22 May
Laboratories and facilities at CIEMAT’s headquarters
9:00 - 10:10
Stellarator TJ-II
Liquid metals laboratory
Grupo swap
Visit exchange
Session type: ADDITIONAL INFORMATION
MEETING ERMSAR VENUE 9:15
22 May
Simulators at Westinghouse facilities - BUS 2
9:15 - 9:30
Session type: Technical Visit
Bus departure
22 May
Simulators at Westinghouse facilities - BUS 2
9:30 - 10:15
Session type: Technical Visit
Arrival to Westinghouse premises
22 May
Simulators at Westinghouse facilities - BUS 1
9:45 - 10:00
Session type: Technical Visit
Severe accident simulator (ASSAS) (*)
22 May
Simulators at Westinghouse facilities - BUS 1
10:00 - 10:35
Session type: Technical Visit
Coffee break
22 May
Laboratories and facilities at CIEMAT’s headquarters
10:10 - 10:50
Session type: Technical Visit
Arrival to Westinghouse premises
22 May
Simulators at Westinghouse facilities - BUS 2
10:15 - 10:30
Session type: Technical Visit
Severe accident simulator (ASSAS) (*)
22 May
Simulators at Westinghouse facilities - BUS 2
10:30 - 11:05
Session type: Technical Visit
AP1000 simulator(*)
22 May
Simulators at Westinghouse facilities - BUS 1
10:35 - 11:10
Session type: Technical Visit
Facilities of the Material Department
22 May
Laboratories and facilities at CIEMAT’s headquarters
10:50 - 11:30
Metallurgy laboratory
Corrosion laboratory
Visit exchange
Transfer to facilities of Fission Dep.
Session type: Technical Visit
AP1000 simulator (*)
22 May
Simulators at Westinghouse facilities - BUS 2
11:05 - 11:40
Session type: Technical Visit
PWR-KWU simulator (*)
22 May
Simulators at Westinghouse facilities - BUS 1
11:10 - 11:50
Session type: Technical Visit
Facilities of the Fission Department
22 May
Laboratories and facilities at CIEMAT’s headquarters
11:20 - 12:10
Nuclear data laboratory
Neutron standard laboratory
Group Swap
Visit exchange
Session type: Technical Visit
PWR-KWU simulator (*)
22 May
Simulators at Westinghouse facilities - BUS 2
11:40 - 12:20
Session type: Technical Visit
Bus departure to Madrid
22 May
Simulators at Westinghouse facilities - BUS 1
11:50 - 12:35
Session type: Technical Visit
Bus departure to Madrid
22 May
Simulators at Westinghouse facilities - BUS 2
12:20 - 13:05
Session type: Technical Visit
Arrival to ERMSAR venue
22 May
Simulators at Westinghouse facilities - BUS 1
12:35 - 12:40
Session type: Technical Visit
Arrival to ERMSAR venue
22 May
Simulators at Westinghouse facilities - BUS 2
13:05 - 13:10
Session type: ADDITIONAL INFORMATION
(*) The order of simulator visits may change due to availability and organizational concerns at Westinghouse
22 May
Simulators at Westinghouse facilities - BUS 1
14:00 - 14:00
Session type: ADDITIONAL INFORMATION
(*) The order of simulator visits may change due to availability and organizational concerns at Westinghouse
22 May
Simulators at Westinghouse facilities - BUS 2
14:00 - 14:00
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