ERMSAR 2012, Cologne, March 21 – 23, 2012 Hydrogen Stratification in Experimental Facilities and PWR Containments – Results and Conclusions of Selected.

Slides:



Advertisements
Similar presentations
Generic Pressurized Water Reactor (PWR): Safety Systems Overview
Advertisements

CSNI/WG-RISK – LEVEL 2 PSA AND ACCIDENT MANAGEMENT WORKSHOP – MARCH ADVANCED MODELING AND RESPONSE SURFACE METHODOLOGY FOR PHYSICAL MODELS OF LEVEL.
Lesson 18 - Decay Heat DEFINE the term decay heat. Given the operating conditions of a reactor core and the necessary formulas, CALCULATE the core decay.
Jiří Duspiva Nuclear Research Institute Řež, plc. Nuclear Power and Safety Division Dept. of Reactor Technology 11 th International QUENCH Workshop Karlsruhe,
HPT Rev. 2 Page 1 of 17 TP-1 ACADs (08-006) Covered Keywords History, post-accident sample, containment air, three mile island, NUREG 0578, NUREG.
PRACTICAL EXAMPLES OF THE ANALYSIS OF SEVERE ACCIDENTS Presented Dr. Chris Allison Regional Workshop on Evaluation of Specific Preventative and Mitigative.
GENERATION III AND III+ NUCLEAR POWER PLANT DESIGNS ACR-1000 (Advanced CANDU Reactor) Dr. Şule Ergün Hacettepe University Department of Nuclear Engineering.
Issues Associated with the Development of Severe Accident Management Guidelines for CANDU Reactors Keith Dinnie Director, Risk Management Nuclear Safety.
CRP on Natural Circulation Phenomena, Modelling and Reliability of Passive Safety Systems that Utilize Natural Circulation September, 2007, IAEA,
Lesson 25 TWO-PHASE FLUID FLOW
Institute for Electric Power Research Co. International Workshop On Level 2 PSA and Severe Accident Management Cologne, Germany 29.
ICHS 2007, San Sebastian, Spain 1 SAFETY OF LABORATORIES FOR NEW HYDROGEN TECHNIQUES Heitsch, M., Baraldi, D., Moretto, P., Wilkening, H. Institute for.
October 25-27, th International QUENCH Workshop 1 Top Flooding Experiments and Modeling Estelle Brunet-Thibault (EDF), Serge Marguet (EDF)
Forschungszentrum Jülich in der Helmholtz-Gemeinschaft E.-A. Reinecke, S. Kelm, S. Struth, Ch. Granzow, U. Schwarz* Catalytic recombiners Design studies.
Overview of Incident at Fukushima Daiich Nuclear Power Station (1F) (Informal personal observations) April 2011.
May 22nd & 23rd 2007 Stockholm EUROTRANS: WP 1.5 Task Containment Assessment IP-EUROTRANS DOMAIN 1 Design WP 1.5 Safety Assessment of the Transmutation.
Safety Features at KKNPP Insight of. Location: The Kudankulam is located on the coast of the Gulf of Mannar, at 25 kM to the north- east from Kanyakumari,in.
SARNET – Severe Accident Research Network University of Manchester School of Mechanical Engineering, G. Begg Building CFD Workshop on Test-Cases, Databases.
KIT – University of the State of Baden-Wuerttemberg and National Laboratory of the Helmholtz Association Institute for Nuclear and Energy Technologies.
 Glowing ball of gas in space which generates energy through nuclear fusion in its core  Closest star to Earth is the Sun.
Overview of Conventional 2-loop PWR Simulator. PCTRAN Dr
Nuclear disaster 3 mile. History In 1979 at three mile nuclear power plant which is in the united states. A cooling malfunction caused part of the core.
Thermal Hydraulic Simulation of a SuperCritical-Water-Cooled Reactor Core Using Flownex F.A.Mngomezulu, P.G.Rousseau, V.Naicker School of Mechanical and.
Idaho National Engineering and Environmental Laboratory Assessment of Margin for In-Vessel Retention in Higher Power Reactors 2004 RELAP5 International.
ASTEC validation on PANDA tests A. BENTAIB, A. BLEYER Institut de Radioprotection et de Sûreté Nucléaire BP 17, Fontenay aux Roses Cedex, FRANCE.
26-27 September 2005 Colloque GDR Intéraction Fluide-Structure, Sophia Antipolis 1 Fluid-Structure Interaction Modelling with Europlexus Fast Dynamics.
J. Eyink*, T. Froehmel**, H. Loeffler*** *Framatome-ANP GmbH, Erlangen, Germany **Bundesamt für Strahlenschutz (BfS), Salzgitter, Germany ***Gesellschaft.
LBE-Water interaction in LIFUS V facility under different operating conditions A. Ciampichetti, D. Bernardi - ENEA T. Cadiou - CEA N. Forgione – Università.
Mitglied der Helmholtz-Gemeinschaft Simulation of the efficiency of hydrogen recombiners as safety devices Ernst-Arndt Reinecke, Stephan Kelm, Wilfried.
Explosion An explosion is a rapid expansion of gases resulting in a rapid moving pressure or shock wave. The expansion can be mechanical or it can be.
ICHS, September 2007 On The Use Of Spray Systems: An Example Of R&D Work In Hydrogen Safety For Nuclear Applications C. Joseph-Auguste 1, H. Cheikhravat.
Fukushima Daiichi Nuclear Plant Event Summary and FPL/DAEC Actions.
Chapter 2 Review. Define matter. Anything that has mass & takes up space.
MODELLING OF MULTIPHASE FLOWS OVER SURFACE WITH PENETRABLE ROUGH RELIEF Yevgeniy A. Shkvar National Aviation University, Kyiv, Ukraine
ERMSAR 2012, Cologne March 21 – 23, 2012 Source term assessment with ASTEC and associated uncertainty analysis using SUNSET tool K. Chevalier-Jabet 1,
ERMSAR 2012, Cologne March 21 – 23, The Experimental Results of LIVE-L8B: Debris Melting Process in a Simulated PWR Lower Head X. Gaus-Liu, A. Miassoedov,
ERMSAR 2012, Cologne March 21 – 23, 2012 ESTIMATION OF THERMAL-HYDRAULIC LOADING FOR VVER-1000 UNDER SEVERE ACCIDENT SCENARIO Barun Chatterjee 1, Deb Mukhopadhyay.
ERMSAR 2012, Cologne March 21 – 23, 2012 MELCOR Severe Accident Simulation for a “CAREM-like” Integral Reactor M. Caputo, J. M. García, M. Giménez, S.
Validation studies of CFD codes on hydrogen combustion
Fukushima Power Plant – Japan Post March 11, 2011
Wir schaffen Wissen – heute für morgen A. Dehbi, D. Suckow, T. Lind, S. Guentay Paul Scherrer Institut, Switzerland Large Scale Experimental Program at.
ERMSAR 2012, Cologne March 21 – 23, 2012 Analysis of Corium Behavior in the Lower Plenum of the Reactor Vessel during a Severe Accident Rae-Joon Park,
CHOOSE EXPERTS, FIND PARTNERS Parametrical study on MCCI reactor cases under dry cavity conditions for assessment of parameters of importance Philippe.
ERMSAR 2012, Cologne March 21 – 23, 2012 Experimental Determination and Analysis of Iodine Mass Transfer Coefficients from THAI Test Iod-23 K. FISCHER,
Natural Convection as a Passive Safety Design in Nuclear Reactors
0 Overview of Fukushima-Accident Analysis ERMSAR 2012, Cologne (Germany) March 21 – 23, 2012 JNES Masanori FUKASAWA.
ERMSAR 2012, Cologne March 21 – 23, 2012 Authors: PANTYUSHIN S.I., FRIZEN Е.А., SEMISHKIN V.P., BUKIN N.V, BYKOV M.А., MOKHOV V.А. (OKB «GIDROPRESS», Podolsk.
ERMSAR 2012, Cologne March 21 – 23, ON THE ROLE OF VOID ON STEAM EXPLOSION LOADS.
ERMSAR 2012, Cologne March 21 – 23, 2012 MOCKA Experiments on Concrete Erosion by a Metal and Oxide Melt J. J. FOIT, T. CRON, B. FLUHRER, A. MIASSOEDOV,
ERMSAR 2012, Cologne March 21 – 23, 2012 In-vessel retention as retrofitting measure for existing nuclear power plants M. Bauer, Westinghouse Electric.
ERMSAR 2012, Cologne March 21 – 23, 2012 Experiments of the LACOMECO Project at KIT A. M IASSOEDOV 1, M. K UZNETSOV 1, M. S TEINBRÜCK 1, S. K UDRIAKOV.
ERMSAR 2012, Cologne March 21 – 23, 2012 Experimental and computational studies of the coolability of heap-like and cylindrical debris beds E. Takasuo,
Results of First Stage of VVER Rod Simulator Quench Tests 11th International QUENCH Workshop Forschungszentrum Karlsruhe October 25-27, 2005 Presented.
ERMSAR 2012, Cologne March 21 – 23, 2012 GENERIC CONTAINMENT A first step towards bringing (European) containment simulations to a common level St. Kelm.
ERMSAR 2012, Cologne March 21 – 23, 2012 ASTEC V2.0 rev 1 Reactor Applications French PWR 900 MWe Accident Sequences Comparison with MAAP4 V. Lombard,
ERMSAR 2012, Cologne March 21 – 23, 2012 EXPERIMENTAL STUDY OF HYDROGEN COMBUSTION DURING DCH EVENTS IN TWO DIFFERENT SCALES Giancarlo Albrecht Leonhard.
Contamination Control Study: BSC Chamber LIGO Observatory Project Number: FVMS Parametric-1 Results August 14, 2006.
ERMSAR 2012, Cologne March 21 – 23, 2012 Post-test calculations of CERES experiments using ASTEC code Lajos Tarczal 1, Gabor Lajtha 2 1 Paks Nuclear Power.
I Overview of EU-APR1400 II Design Concept of Safety Systems III
Plant & Reactor Design Passive Reactor Core Cooling System
Post-Fukushima Severe Accident Management Update Kim, Hyeong Taek KHNP- Central Research Institute July KINS Safety Analysis Symposium.
A.Borovoi, S.Bogatov, V.Chudanov, V.Strizhov
Approaches and measures aimed at ensuring safety, preventing severe accidents in new RF NPP designs Gutsalov N.A. 10/03/2016.
Lesson 24 NATURAL CIRCULATION
T. Steinrötter, M. Kowalik, H. Löffler, M. Sonnenkalb, I. Bakalov
Pressurized Water Reactor
Review of the upgraded severe accident mitigation strategies for the generation II PWRs in France foreseen in the framework of plant life extension International.
Session Name: Lessons Learned from Mega Projects
Mixing of the Atmosphere within the EPR Design Containment in Design Basis and Severe Accident Conditions Prof. Ali Tehrani ONR Principal Inspector –
Approaches and measures aimed at ensuring safety, preventing severe accidents in new RF NPP designs Gutsalov N.A. 10/03/2016.
Presentation transcript:

ERMSAR 2012, Cologne, March 21 – 23, 2012 Hydrogen Stratification in Experimental Facilities and PWR Containments – Results and Conclusions of Selected COCOSYS Simulations S. Schwarz, S. Band, M. Sonnenkalb GRS Germany

ERMSAR 2012, Cologne, March 21 – 23, 2012 – During a severe accident hydrogen (H 2 ) could be generated in the reactor coolant system (RCS) – In case of a release at an elevated position in the containment -> atmospheric stratification -> high H 2 concentrations above and low H 2 concentrations below the release position – Stratification can be dissolved by different processes – H 2 distribution in containment -> flammability – Experiments, COCOSYS validated: THAI, PANDA, HDR E11.2 – PWR application by COCOSYS 2

ERMSAR 2012, Cologne, March 21 – 23, 2012 HDR containment COCOSYS nodalisation 143 nodes inclusive annular compartments and gap E11.2 experiment 0 – 12.5 h: upper steam injection – h: H 2 /He injection – 16 h: lower steam injection – 20 h: spraying upper hemisphere after 20 h: natural cooldown, venting 3

ERMSAR 2012, Cologne, March 21 – 23, H2/He concentrations experiment, COCOSYS injection phase Hydrogen stratification Light gas cloud (H2/He, air steam) in upper region

ERMSAR 2012, Cologne, March 21 – 23, H 2 /He concentrations experiment and COCOSYS during lower steam injection and 1st part of spraying -Concentrations at different elevations -Same elevation -> same color for COCOSYS and experiment Hydrogen stratification in dome Contraction of light gas cloud Simulated by COCOSYS Contraction accelerated during spraying

ERMSAR 2012, Cologne, March 21 – 23, H 2 /He concentrations experiment and COCOSYS 2 nd part of spraying and remaining test Mixing of atmosphere Partial dilution of stratification by outside spraying Simulated by COCOSYS

ERMSAR 2012, Cologne, March 21 – 23, PWR containment steel shell diameter 56 m equipment compartments separated by doors and rupture elements from rest of containment Passive Autocatalytic Recombiner (PAR) concept with ~60 devices COCOSYS nodalisation: 281 zones inclusive annular compartments and gap

ERMSAR 2012, Cologne, March 21 – 23, Core melt scenario “ND*” Loss of SG-feed No ECCS available Release from RCS/Prz. at an elevated position Main events:  1.4 h start steam release from RCS/Prz.  2.2 h start H 2 release from RCS/Prz.  6.4 h start release by MCCI in cavity  17.1 h start melt - sump water contact

ERMSAR 2012, Cologne, March 21 – 23, Hydrogen concentrations dome and equipment compartments Hydrogen generation in equipment compartments, difference to E11.2 Mixing of dome, combination of heat sinks and sources, difference to E11.2 Hydrogen stratification in equipment compartments

ERMSAR 2012, Cologne, March 21 – 23, Hydrogen concentrations dome and compartments behind missile protection Hydrogen stratification behind missile protection

ERMSAR 2012, Cologne, March 21 – 23, Summary, conclusions – COCOSYS was validated successfully against several stratification experiments; here the example HDR E11.2 was shown.. – A hydrogen release at an elevated position can create an atmospheric stratification – high hydrogen concentrations at and above the release position an low concentrations below. – Same for experiments (f.e. HDR E11.2) and the PWR calculation. – PWR in addition: stratification behind missile protection. – The dilution of the stratification as observed in E11.2 cannot be compared with the PWR calculation because the boundary conditions differed strongly between both cases.