ERMSAR 2017

ERMSAR 2017, hosted by NCB at Warsaw, Poland, 16-18 May 2017
8th conference on Severe Accident Research

- The announcement.

- The final programme.

PAPERS

Plenary sessions

101 Paper - Recent Contributions of OECD-WGAMA to the Severe Accident Field.pdf
102 Paper -  Behaviour of radionuclides in continental hydrosystems following a severe accident theoretical, experimental and modelling approaches.pdf
103 Paper - Overview of the Severe Accident Analysis Program in Korea.pdf
1001 Paper - Severe Accident Mitigation and Modelling Requirements for New Build Reactors.pdf

Ex-vessel corium interactions and coolability

201 Abstract  - Corium spreading under water and its possible consequences.pdf
202 Paper - Concrete Decomposition Temperature relevant to MCCI Process on LCS concrete.pdf
203 Paper -  Stratified Steam Explosion Phenomena Analysis of the SAFEST SES-S1 Test.pdf
204 Paper - Fabricating Fukushima Daiichi in-vessel and ex-vessel fuel debris simulants for the development and qualification of laser cutting technique.pdf
205 Paper - Experiment and Modeling of Jet Breakup in Fuel-Coolant Interactions.pdf
206 Paper - Study on thermal fragmentation characteristics of a superheated alumina droplet.pdf
207 Paper - MC3D Premixing Analysis using X-Ray Radioscopy Experimental Data of KROTOS-SERENA Tests.pdf
208 Paper - Improvement of molten jet fragmentation modeling in MAAP.pdf
209 Paper - Towards CFD-grade measurements in a condensing boundary layer - first results of the new SETCOM facility.pdf

Source Term issues

301 Paper - Source Term Mitigation in Suppression Pools under Jet Injection Regime ASTEC-CPA Predictability.pdf
302 Paper - Main Results of the European PASSAM Project on Severe Accident Source Term Mitigation.pdf
303 Paper - Validation of COCOSYS Fission Product Models by AREVA.pdf
304 Paper - Interaction and Depletion Behaviour of Representative Core Melt Aerosols.pdf
305 Paper -  Results and Progress of Fundamental Research on FP Chemistry.pdf
306 Paper - Agglomeration of nuclear aerosols under the effect of intense acoustic fields as pre-condition for FCVS retention.pdf
307 Paper - An innovative Method to study Volatile Fission Products speciation in nuclear fuels under Severe Accident Conditions.pdf
308 Paper - Modeling of Fission Product scrubbing in experiments and in integral severe accident scenarios.pdf
309 Paper - Experimental-study-of-pressure-drop-in-self-priming-venturi-scrubber.pdf
310 Paper - The effect of post-accident pH control on iodine behaviour in the containment.pdf

Containment behaviour incl H2 explosion risk

401 Paper - Application of CFD in Hydrogen Safety Management.pdf
402 Paper - Experimental Investigations on Containment Spray Performance under Severe Accident Conditions.pdf
403 Paper - Thermofluid Dynamic Analysis for THAI Tests with Passive Hydrogen Recombiner.pdf
404 Paper - Benchmark exercise TH27 on natural convection with steam injection and condensation inside the extended THAI facility.pdf
405 Paper - The Influence of Thermal Radiation on the Free Convection inside Enclosures.pdf
406 Paper - Coupling Approach for the CFD Code CFX and the Lumped Parameter Code COCOSYS and First Results.pdf
407 Paper - Modeling the start-up behavior of passive auto-catalytic recombiners in REKO-DIREKT.pdf

 

In-vessel corium and debris coolability

501 Paper - Validation Progress and Exploratory Analyses of Three-Dimensional Simulation for BWR In-Vessel Core Degradation.pdf
502 Paper - CoreSOAR Core Degradation State-of-the Art Report Update Status May 2017.pdf
503 Paper - Status of the IVMR project First steps towards a new methodology to assess In-Vessel Retention Strategy for high-power reactors.pdf
504 Paper - Modeling issues related to molten pool behavior in case of In-Vessel Retention Strategy.pdf
505 Paper -  Contribution of CFD studies to IVR assessment.pdf
506 Paper - Rayleigh-Bénard and Bénard-Marangoni convection in a thin metallic layer on top of corium pool.pdf
507 Paper - In-vessel corium modelling in the MAAP5_EDF code.pdf
508 Paper - COMPASS - new modeling and simulation approach to PWR in-vessel accident progression.pdf
509 Paper - Assessment and calibration of an algebraic turbulent heat flux model for high Rayleigh number flow regimes.pdf
510 Paper - Modeling of melt pool formation during IVMR using the HEFEST-URAN code.pdf
511 Paper - Study on the distribution of boron in the in-vessel fuel debris in conditions close to Fukushima Daiichi Nuclear Power Station Unit 2.pdf
512 Paper - On the use of CALPHAD-based enthalpy-temperature relations in suboxidized corium plane front solidification modelling.pdf
513 Paper - New Modeling in the MAAP Code for the Oxidation of Zr-Based Fuel Claddings in Steam and Air-Steam Mix under Severe Accident Conditions.pdf
514 Paper - Experimental and Numerical Investigation of Molten Corium Behavior in Lower Head under External Subcooling and Boiling Conditions.pdf
515 Paper - Comparison of turbulent heat flux models for a volumetrically heated liquid pool.pdf

Severe accident scenarios

601 Paper- Simulation of thermal hydraulics accidental transients - New evaluations and acceleration of MAAP5.02 versus CATHARE.pdf
602 Paper - Studies on the Recriticality Potential during Fukushima Unit-3 Core Reflooding.pdf
603 Paper - Sensitivity analysis for modeling of severe accidents with CC SOCRATB1.pdf
604 Paper - In-Vessel Retention Analysis for PHWR Calandria under Severe Core Damage Accident Condition using ASTEC.pdf
605 Paper - Prevention of Core Damage due to Total Loss of Power and Extreme External Events by Independent Core Cooling in Swedish NPP– Background and Design Principles.pdf
606 Paper - Severe accident code to code comparison for two accident scenarios in a spent fuel pool.pdf
607 Paper - Impact of Potential Accident Mitigation Strategies and Characteristics of Source Term Release for Representative SFP Severe Accident Scenarios.pdf
608 Abstract - CFD modeling of molten metal injection in water pool.pdf
609 Paper - ASTEC Investigations of Accident Management Measures for a Station Black-Out (SBO) Scenario of a Generic German PWR Plant.pdf
610 Paper - Comparison of accident transients in AP600 and AP1000 “like” models based on a modified LBLOCA.pdf
611 Paper - Insight of core degradation simulation in integral codes throughout ASTECMELCOR crosswalk comparisons and ASTEC sensitivity studies.pdf
613 Paper - The Progress of ALISA Project.pdf
614 Abstract - In Vessel Melt Retention Strategy-Status of work for VVER 1000.pdf
616 Paper - CESAM – Code for European Severe Accident Management, EURATOM project on ASTEC improvement.pdf

SLIDES

Plenary sessions

NCBJ general presentation.pdf
Overview of NUGENIA TA2SARNET status.pdf
EURATOM Research activities related to severe accidents within H2020.pdf
101 - Recent Contributions of OECD-WGAMA to the Severe Accident Field.pdf
102 - Behaviour of radionuclides in continental hydrosystems following a severe accident theoretical, experimental and modelling approaches.pdf
103 - Development of an Integrated Severe Accident Analysis Computer Program Package in Korea.pdf
104 -  FASTNET  FAST Nuclear Emergency Tools.pdf
1001 - Severe Accident Mitigation and Modelling Requirements for New Build Reactors.pdf
1003 - How Polish safety requirements can be satisfied.pdf
701 - The Tyranny of Severe Accident Management.pdf
702 - Focussing Severe Accident Research for Accident Management Applications.pdf
Conclusions - ERMSAR 2017.pdf

Ex-vessel corium interactions and coolability

201 - Corium spreading under water and its possible consequences.pdf
202 - Concrete decomposition temperature relevant to MCCI process.pdf
203 - Stratified Steam Explosion Phenomena SAFEST SES-S1 test results and preliminary analysis.pdf
204 - Fabricating Fukushima Daiichi in-vessel and ex-vessel fuel debris simulants for the development and qualification of laser cutting technique.pdf
205 - Experiment and Modeling of Jet Breakup in Fuel-Coolant Interactions.pdf
206 - Study on thermal fragmentation characteristics of a superheated alumina droplet.pdf
207 - MC3D Premixing Analysis using X-Ray Radioscopy Experimental Data of KROTOS-SERENA Tests.pdf
208 - Improvement of molten fragmentation  modeling in MAAP.pdf
209 - Towards CFD-grade measurements in a condensing boundary layer First results of the new SETCOM facility.pdf
211 - Spreading on wet substrates in KATS experiments.pdf

Source Term issues

301 - Mitigation of Source Term in Suppression Pools.pdf
302 - Main Results of the European PASSAM Project on Severe Accident Source Term Mitigation.pdf
303 - Validation of COCOSYS Fission Product Models by AREVA.pdf
304 - Interaction and Depletion Behaviour of Representative Core Melt Aerosols in Presence of Fire Products.pdf
305 - Results and Progress of Fundamental Research on FP Chemistry.pdf
306 - Agglomeration of nuclear aerosols under the effect of intense acoustic fields as pre-condition for FCVS Retention.pdf
307 - An innovative Method to study Volatile Fission Products speciation in nuclear fuels under Severe Accident conditions.pdf
308 - Modeling of FP scrubbing in experiments and.pdf
310 - The effect of post-accident pH control on iodine behavior in the containment.pdf

Containment behaviour incl H2 explosion risk

401 - Application of CFD in Hydrogen Safety Management.pdf
402 - Experimental Investigations on Containment Spray Performance under Severe Accident Conditions.pdf
403 - Thermofluid Dynamic Analysis for THAI Tests with Passive Hydrogen Recombiner.pdf
404 - Benchmark exercise TH27 on natural convection with steam injection and condensation inside the extended THAI facility.pdf
405 - The Influence of Thermal Radiation on the Free Convection inside Enclosures.pdf
406 - Coupling Approach for the CFD Code CFX and the Lumped Parameter Code COCOSYS and First Results.pdf
407 - Modeling the start-up behavior of passive auto-catalytic recombiners in REKO-DIREKT.pdf

 

In-vessel corium and debris coolability

501 - Validation Progress and Exploratory Analyses of Three-Dimensional Simulation for BWR In-vessel Core Degradation.pdf
502 - Presentation_CoreSOAR.pdf
503 - Status of the IVMR project First steps towards a new methodology to assess In-Vessel Retention Strategy for high-power reactors.pdf
504 - Modelling issues related to molten pool behaviour in case of In-Vessel Retention Strategy.pdf
505 - Contribution of CFD studies to IVR assessment.pdf
506 - Rayleigh-Benard And Benard-Marangoni Convection In A Thin Metallic Layer On Top Of Corium Pool.pdf
507 - In-vessel prospective corium modelling in the MAAP_EDF.pdf
509 - Assessment and calibration of an algebraic turbulent heat flux model for high Rayleigh number flow regimes.pdf
510 - Modeling of Melt Pool Formation during IVMR Using the HEFEST-URAN Code.pdf
511 - Study on the distribution of boron in the in-vessel fuel debris in conditions close to Fukushima Daiichi Nuclear Power Station Unit 2.pdf
512 - On The Use Of CALPHAD-Based  Enthalpy-Temperature Relations In Suboxidized  Corium Plane Front Solidification Modelling.pdf
514 - Experimental and Numerical Investigation of Molten Corium Behavior in Lower Head under External Subcooling and Boiling Conditions.pdf
515 - Computation of turbulent natural convection with buoyancy corrected second moment closure models.pdf
516 - Imaging of nuclear fuel debris using ultrasonic arrays.pdf
517 - The SAFEST project towards pan-European Lab on Corium Behavior in Severe Accidents. Main Objectives and R&D priorities.pdf
518 - Melting Test of Penetrating Tube through BWR-RPV Bottom Wall.pdf

Severe accident scenarios

601 - Simulation of thermal hydraulics accidental transients new evaluations and acceleration of MAAP5.02 versus CATHAREv2.5.pdf
602 - Studies on recriticality potential during Fukushima Unit 3 Core reflooding.pdf
603 - Sensitivity analysis for modeling of severe accidents with SOCRATB1 computer code.pdf
604 - In-Vessel Retention Analysis for PHWR Calandria under Severe Core Damage Accident Condition using ASTEC.pdf
605 - Prevention of Core Damage due to Total Loss of Power and Extreme External Events by Independent Core Cooling in Swedish Nuclear Power Plants.pdf
606 - Severe accident code-to-code comparison for two accident scenarios in a Spent Fuel Pool.pdf
607 - Impact of Potential Accident Mitigation Strategies and Characteristics of Source Term Release for Representative SFP Severe Accident Scenarios.pdf
608 - CFD modeling of molten metal injection in water pool.pdf
609 - ASTEC Investigations of Accident Management Measures for a Station Black-Out (SBO) Scenario in a Generic German Konvoi PWR.pdf
610 - Comparison of accident transients in AP600 and AP1000 like models based on a modified LBLOCA.pdf
611 - Insight of core degradation simulation in integral codes throughout ASTECMELCOR crosswalk comparisons.pdf
613 - The Progress of ALISA Project Access to Large Infrastructures for Severe Accidents in Europe and in China.pdf
614 - In Vessel Melt Retention Strategy – Status of work for VVER 1000.pdf
616 - CESAM - Code for European Severe Accident Management EURATOM project on ASTEC improvement.pdf
617 - The Severe Accident Phenomenology Short Course (SAP) 12 years of excellence for dissemination of severe accident knowledge at international level.pdf

POSTERS

Containment behaviour incl.H2 explosion risk

451 Abstract - Numerical Study on flame acceleration in obstructed duct using FLUENT.pdf
452 Abstract - Simulation of Containment Gas and Water Flow using cosSA.pdf

Ex-vessel corium interaction and coolability

210 Paper - Analysis of melt-coolant energetic interaction in the course of the in-vessel phase of severe accidents on NPP with WWER.pdf
251 Abstract - Interpretation of recent MOCKA experiments on MCCI of a stratified melt with reinforced concrete by means of the MEDICIS code.pdf
252 Abstract - Experimental and mathematical assessment of ex-vessel melt pool coolability under bottom flooding.pdf
253 Abstract - CFD modeling of molten metal injection in water pool.pdf

In-vessel corium and debris coolability

553 Paper - Thermal Load Analysis and IVR Margin Evaluation for Small Modular Reactor.pdf
554 Abstract - Cold crucible facilities in Rez.pdf

 

Severe accident scenarios

651 Paper - Analysis of TMI-2 Scenario using CSPACE Computer Code.pdf
652 Abstract - The Express Method of Nuclear Safety Analysis at Modernization of VVER.pdf
653 Paper - Usability Evaluation and Qualification Methodology of Equipments for Severe Accident.pdf
654 Abstract - A Stand-alone Containment analysis of the Phébus FPT-0 test with the ASTEC and the MELCOR codes.pdf
655 Abstract - Analysis of steam generator heat exchanging tubes integrity on the in-vessel phase of severe accidents on NPP with WWER.pdf
656 Paper - Development and Study of a SBO on CANDU6 Plant Model using Grape.pdf
657 Abstract - Modeling of the Fukushima Accident with MELCOR.pdf
658 Paper - Application of ATHLET-CD code for simulation of SBLOCA 50 cm² severe accident scenario for a generic German PWR.pdf
659 Abstract - Development of the SARCAM Computer Code.pdf

Source term issues

351 Abstract - Tellurium Transport in Nuclear Power plants.pdf
352 Abstract - Integration of Pool scrubbing Research to Enhance Source-term Calculations (IPRESCA).pdf
353 Abstract - Summary of the Nordic collaboration Impact of air radiolysis, FP and CR species on the transport of ruthenium in the primary circuit of NPP in a SA.pdf