ÚJV Řež, a. s.


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Programme

Programme

 

Monday, March 18, 2019

PLENARY SESSION:   Introductory part
  Chair J. Duspiva, ÚJV Řež, a.s.
 
8:30 Registration
9:15 Opening
9:25 UJV introductory speech
D. Jiřička ÚJV Řež, a.s.
9:40 Overview of NUGENIA TA2/SARNET Status
L. Herranz CIEMAT/ NUGENIA TA2
                         
10:10 Coffee break
                         
  Session 1-1 In-vessel corium and debris coolability Session 2 Emergency management and severe accident impact on the environment
  Chair: A. Miassoedov, IAEA Chair: F. Bréchignac, IRSN
10:30 Status of Test Facility to Confirm the IVMR Strategy for VVER 1000/320 2 SOARCA Uncertainty Analysis of a Short-Term Station Blackout Accident at the Sequoyah Nuclear Power Plant 97
  J. Zdarek, et al. UJV Rez, a. s. N. Bixler SNL
10:55 Experimental studies of molten steel - suboxidized corium crust interaction for IVR application 5 ALISA Project: Access to Large Infrastructures for Severe Accidents in Europe and in China 90
  P. Piluso et al. CEA Cadarache X. Gaus-Liu et al. KIT Karlsruhe
11:20 The CMMR Program: BWR Core Degradation in the CMMR-4 test 12 SAFEST Project on Corium Behavior in Severe Accidents 89
  Takuya Yamashita, Ikken Sato JAEA B. Fluhrer et al. KIT Karlsruhe
11:45 CoreSOAR Core Degradation State-of-the Art
Report Update: Conclusions
22 Severe Accident Research Priority ranking: a new assessment eight years after the Fukushima Daiichi accident 98
  T. Haste et al. IRSN D. Bottomley et al. JAEA-CLADS Lab.
                         
12:10 Lunch

 

PLENARY SESSION:   Invited Contributions
  Chair A. Bentaib, IRSN/NUGENIA TA2
 
14:00 Improvement of Safety of Czech NPPs i1
B. Zronek ČEZ, a.s.
14:30 Severe Accident Modelling Evolution and Perspectives i2
R. Gauntt SNL
15:00 Current status and recent investigation result of Fukushima Daiichi i3
S. Mizokami TEPCO
                         
15:40 Coffee break
                         
  Session 1-2 In-vessel corium and debris coolability Session 3-1 Severe accident scenarios
  Chair: A. Miassoedov, IAEA Chair: F. Rocchi, ENEA
16:00 Study of a Thin Metallic Layer: Comparison of CFD and Integral Codes 23 Strategy of Corium Localization for VVERs under Severe Accident Conditions 3
  C. Le Guennic EdF Yu. Zvonarev, Yu. Semchenkov NRC «KI»
16:25 Consistent use of CALPHAD data for in-vessel corium pool modeling: some analytical and practical considerations 33 Sump plugging issue concerning NPP
Experimental Program on Chemical Effects
Impact of insulation composition: possible creation of sodium silicate
6
  R. Le Tellier et al. CEA Cadarache
J. Batalik, V. Soltesz et al.
VUEZ, a.s.
16:50 Experimental study on the influence of the downward facing surface characteristics on CHF 35 Validation of ASTEC2.1 using QUENCH-12 for VVER-reactors 11
  B. Lin et al. CNPRI A. Mercan, et al. KIT Karlsruhe
17:15 ASTEC simulation of In Vessel Retention Strategy applied to a generic PWR 900 MWe 38 Ongoing Severe Accident Analysis at Sandia National Laboratories 108
  F. Mascari et al. ENEA-BOLOGNA N. Andrews et al. SNL
17:40 Adjourn      

 

Tuesday, March 19, 2019

  Session 1-3 In-vessel corium and debris coolability Session 3-2 Severe accident scenarios
  Chair: F. Gabrielli, KIT Chair: F. Rocchi, ENEA
8:30 Main outcomes from the IVR code benchmark performed in the IVMR project 39 Investigation of the Effect of the Spent Fuel Pool Configuration on Fuel Degradation 21
  L. Carenini et al. IRSN L. Lovasz et al. GRS
8:55 CFD Simulations of Melt-Vessel Interaction in Context of IVMR Problem 44 Challenges and sensitivities in the modelling of Fukushima Unit 1 unfolding with MELCOR 2.2 30
  A. Filippov, D. Kamenskay RAS IBRAE Luis E. Herranz, Claudia López CIEMAT
9:20 Effect of Prandtl number on thermal behavior in oxide pool with the high Rayleigh number region 50 A preliminary evaluation of the recriticality potential in Fukushima Daiichi debris beds 58
  S. Whang, H.S. Park POSTECH M. Freiría López et al. IKE, Uni of Stuttgart
9:45 Thermalhydraulic DNS of a Thin Metallic Layer: Application to the Evaluation of Nuclear Reactor Severe Accident Mitigation Strategy 61 Sensitivity analysis of in-vessel accident progression behavior in Fukushima Daiichi Nuclear Power Plant Unit 3 with MELCOR 2.2 code 66
  M. Peybernes et al. CEA Cadarache X. Li et al. JAEA
                         
10:10 Coffee break + poster session
                         
  Session 1-4 In-vessel corium and debris coolability Session 3-3 Severe accident scenarios
  Chair: F. Gabrielli, KIT Chair: F. Rocchi, ENEA
11:00 Elaboration of a PIRT for the modelling of In-Vessel Retention 70 State-of-the-Art reactor Consequence Analyses
Project: Uncertainty Analyses for Station Blackout Scenarios
71
  F. Fichot et al. IRSN S.T. Ghosh, D.M. Osborn U.S. NRC
11:25 Experimental Study on the Behaviour of In-Vessel Two-Layer Melt Pool in LIVE2D Facility 72 Evaluation of Severe Accident management Guidance - MAAP5 and MELCOR Simulation - Insights to Enhance Training 73
  X. Gaus-Liu et al. KIT Karlsruhe R. Wachowiak et al. EPRI
11:50 Pre- and Post-Test Simulations of the QUENCH-18
Bundle Experiment in the frame of the NUGENIA QUESA Project
76 BEPU analysis of a Station BlackOut in CANDU reactors with RELAP/SCDAPSIM 75
  A. Vasiliev et al. IBRAE A. Stefanova et al. ISS
12:15 Freezing Plug Formation in PHWR Calandria Vessel Penetrations 94 Evaluation of in-vessel melt retention through external reactor vessel cooling of SMART reactor with CINEMA code package in Korea 83
  J. Spencer, A. Quastel CNL Donggun Son et al. KAERI
                 
12:40 Lunch

 

PLENARY SESSION:   International programs
  Chair A. Beintab, IRSN/NUGENIA TA2
 
14:10 EC – H2020 Projects on Severe accidents i5
R. Passalacqua EC Euratom RTD
14:40 OECD/NEA – Projects on Severe Accidents and WGAMA Activities i4
L. Herranz CIEMAT/ NEA/CSNI WGAMA Chair
15:10 IAEA – CRP Projects on Severe Accidents i6
A. Miassoedov IAEA
                         
15:40 Coffee break + poster session
                         
  Session 1-5 In-vessel corium and debris coolability Session 4-1 SA modelling and code development
  Chair: F. Gabrielli, KIT Chair: S. Paci, Uni Pisa
16:30 CLADS research for Fukushima Daiichi as contribution for the SAFEST Severe Accident Research Programme 95 Application of a newly developped computer code model for nitriding and re-oxidation of cladding materials on separate effect tests and integral experiments 24
  D. Bottomley et al. JAEA-CLADS Lab. B. Jäckel et al. PSI
16:55 Assessment of External Vessel Cooling for In-Vessel Retention 103 A new pool scrubbing module in ASTEC: bubble hydrodynamic and thermalhydraulic modelling aspects 36
  K. Athken EdF C. Marchetto, F. Cousin IRSN
                         
  Session 5-1 Source term issues    
  Chair: L. Herranz, CIEMAT    
17:20 First aerosol results of the QUENCH-18 bundle test 19 Integrated Uncertainty Analysis of Phebus FPT0 experiment using RELAP/SCDAPSIM/MOD3.4 with IUA option 77
  J. Kalilainen et al. PSI A. Salem et al. Alexandria University
17:45 Elemental Iodine Retention inside a Wet Scrubber for Different Flow Regimes relevant for Pool Scrubbing and FCVS 28 Severe Accident Code Development for CANDU reactor in Korea 78
  S. Tietze, P. Papadopoulos PSI J.H. Bae et al. KAERI
18:10 Adjourn
                         
18:30 Conference dinner - Hotel restaurant Benada

 

Wednesday, March 20, 2019

  Session 5-2 Source term issues Session 4-2 SA modelling and code development
  Chair: L. Herranz, CIEMAT Chair: S. Paci, Uni Pisa
8:30 Uncertainty quantification of in-pool fission product retention during BWR Station BlackOut sequences 31 Validation and verification for the melting and eutectic models in JUPITER code 88
  Luis E. Herranz et al. CIEMAT X. Li JAEA
8:55 Modelling of Cesium Chemisorption under Nuclear Power Plant Severe Accident Conditions 47 Overview of ASTEC integral code status and perspectives 96
  F. Miradji et al. JAEA L. Chailan IRSN
      Session 6-1 Ex-vessel corium interactions and coolability
      Chair: P. Piluso, CEA
9:20 Iodine Trapping by Porous Materials to Mitigate Releases to the Environment 54 Impact of Corium Thermophysical Properties on Fuel-Coolant Interaction 9
  L. Cantrel et al. IRSN N. Chikhi et al. CEA Cadarache
9:45 Aerosols Released During the Laser Cuttinf of a Fukushima Daiichi Debris Simulant 92 Analysis of Steam Explosion Duration in Stratified Configuration 10
  Ch. Journeau CEA Cadarache M. Leskovar, et al. JSI
                         
10:10 Coffee break
                         
  Session 7 Containment behavior incl. H2 explosion risk Session 6-2 Ex-vessel corium interactions and coolability
  Chair: I. Kljenak, JSI Chair: P. Piluso, CEA
10:30 Hydrogen Deflagration analyses in THAI experiments using MELCOR code 29 A new two-phase pressure drop model for porous media in boiling conditions for dryout heat flux prediction 42
  A. Flores y Flores et al. CV Rez H. S. Park et al. POSTECH
10:55 Measurements of the Impact of Carbon Monoxide on the performance of Passive Autocatalytic Recombiners at Containmenttypical Conditions in the THAI Facility 55 BWR Lower Plenum Debris Characterization, Stabilization, and Ex-Vessel Transport 49
  M. Freitag et al. B-T GmbH R. Wachowiak et al. EPRI
11:20 Simulation of Experiment on Light Gas Layer Erosion in Small-Scale MCTHBF Containment Experimental Facility 87 Retrofitting of a Generic Ex-Vessel Core Catcher for the Safety Improvement of Operating Nuclear Power Plants, at the Example of a BWR with Mark I Containment 60
  I. Kljenak et al. JSI T. Keim, M. Fischer Framatome GmbH
11:45 Erosion of a stratified layer by a diffuse buoyant jet: controlled experimental parametric variations 101 Melt/Concrete Interface Temperature relevant to MCCI Process 65
  E. Studer et al. CEA Saclay J. Foit et al. KIT Karlsruhe
12:10 Effect of PAR deactivation by carbon monoxide in the late phase of a severe accident 102 Large Scale VULCANO MCCI Test Considering 1F Condition 107
  E.-A. Reinecke et al. FZJ GmbH V. Bouyer et al. CEA Cadarache
                         
12:35 Lunch
                         
  Session 5-3 Source term issues Session 3-4 Severe accident scenarios
  Chair: L. Herranz, CIEMAT Chair: F. Rocchi, ENEA
14:05 Implementation of the Dry Filtered Method (DFM) at VVER-1000 91 Impact of the new SAMGs on Fukushima Daiichi Unit 2 Accident Simulation with MELCOR 2.1 84
  J. Jimenez Escalante Westinghouse Electric Germany R. Bocanegra et al. UPM
14:30 Magnetic filtration trends of multi-functional magnetic nanoparticles with respect to its size and environments during severe accident 93 Benchmark analysis of LB LOCA with reactor cavity flooding for VVER-1000/V320 NPP 85
  D.H. Kam, Y.H. Jeong KAIST M. Kotouc et al. UJV Rez
14:55 Review of knowledge and remaining uncertainties on potential sources of organic iodides in a NPP containment during a severe accident 99 FASTNET Scenarios Database Development - Status and major Outcomes 104
  L. Bosland, J. Colombani IRSN F. Mascari et al. ENEA
         
15:20 Coffee break

 

PLENARY SESSION:   Closing Session
  Chair J. Duspiva, UJV, A. Bentaib, IRSN/NUGENIA TA2
 
  Title, presenter, affiliation, N°
15:40 Summary and conclusions of Session Chairs  
Session Chairs ERMSAR Scietific Committee
16:55 Concluding remark and introduction of ERMSAR2021  
A. Bentaib, L. Herranz NUGENIA TA2 (IRSN, CIEMAT)
17:05 Closing remarks  
J. Duspiva ÚJV Řež, a.s.
17:10 Adjourn

 

Thursday, March 21, 2019

Technical tour to UJV Rez, a. s. – optional program

Visit of experimental facilities

  • THS-15 on VVER1000 RPV coolability under IVR-ERVC strategy
  • LOCA facility – qualification of equipment for DBA and SA conditions
  • Cold Crucible – experimental facility for corium investigation

 

   
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