EUROTRANS – DM1 ENEA Activities on EFIT Safety Analysis ENEA – FIS/NUC Bologna - Italy WP5.1 Progress Meeting Tractebel / Brussels, March 17, 2006 G. Bandini,

Slides:



Advertisements
Similar presentations
A case history of CFD support to Accelerator Driven System plant
Advertisements

Thermal-Hydraulic Transient Analysis of the Missouri University Research Reactor (MURR) TRTR Annual Meeting September 17-20, 2007 Dr. Robert C. Nelson1,
Preliminary T/H Analyses for EFIT-MgO/Pb Reactor Design WP1.5 Progress Meeting KTH / Stockholm, May 22-23, 2007 G. Bandini, P. Meloni, M. Polidori Italian.
EUROTRANS – DM1 RELAP5 Model Evaluation with SIMMER-III Code and Preliminary Transient Analysis for EFIT Reactor WP5.1 Progress Meeting KTH / Stockholm,
LEADER Project: Task 5.4 Analysis of Representative DBC Events of the ETDR with RELAP5 G. Bandini - ENEA/Bologna LEADER 5 th WP5 Meeting JRC-IET, Petten,
LEADER Project: Task 5.4 Analysis of Representative DBC Events of the ETDR with CATHARE G. Geffraye, D. Kadri – CEA/Grenoble G. Bandini - ENEA/Bologna.
HTTF Analyses Using RELAP5-3D Paul D. Bayless RELAP5 International Users Seminar September 2010.
Transmutation and ADS Safety EUROTRANS WP1.5 Meeting, Nov 27-28, Karlsruhe Simulation of EFIT Steam Generator Tube Rupture Accident (U-10) M. Flad, S.
EUROTRANS WP 1.5 Meeting FZK – Karlsruhe, November 27-28, 2008 FPN-FISNUC / Bologna EUROTRANS – DM1 EFIT Transients Analysis with RELAP5, SIMMER-III and.
AREVA NP EUROTRANS WP1.5 Technical Meeting Task – ETD Safety approach Safety approach for EFIT: Deliverable 1.21 Lyon, October Sophie.
Framatome ANP IP-EUROTRANS Meeting WP 1.5 Progress in safety approach development TEE, March Sophie EHSTER.
Transmutation and ADS Safety Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Transient Analysis for EFIT (ENEA 384MWth 3-Zone core) Safety and.
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.
AREVA NP EUROTRANS WP1.5 Technical Meeting Task – Safety approach Madrid, November Sophie EHSTER.
Royal Institute of Technology, Nuclear Power Safety AlbaNova University Center, SE Stockholm, SWEDEN 1 The SGTR Event.
EUROTRANS – DM1 Preliminary Transient Analysis for EFIT with RELAP5 and RELAP/PARCS Codes WP5.1 Progress Meeting Empresarios Agrupados - Madrid, November.
EUROTRANS: WP1.5 Technical meeting, Karlsruhe, November 27 – 28, XT-ADS DHR Conceptual Design L. Mansani
Transmutation and ADS Safety Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft EUROTRANS DM1-WP1.5 Mtg. Stockholm, May 22-23, 2007 Some Recent.
ENGINEERING PROJECT PROPOSAL MASTER OF ENGINEERING IN MECHANICAL ENGINEERING DAN FLAHIVE Analytical Method to Predict Primary Side Steam Generator Pressure.
“Design and safety analysis of ALFRED”
1 Safety studies for MYRRHA B. Arien, S. Heusdains, H. Aït Abderrahim on behalf of the MYRRHA Team and Support IP-Eurotrans Workshop DM1-WP1.5Brussels,
Forschungszentrum Karlsruhe Technik und Umwelt IRS /FzK W.M.SchikorrEUROTRANS WP1.5 Safety Meeting : Karlsruhe, Nov 27-28, EFIT-Pb Transient Analysis.
AREVA NP EUROTRANS WP1.5 Technical Meeting Task – ETD Safety approach Safety approach for EFIT: Deliverable 1.21 Stockholm, May Sophie.
IP EUROTRANS Lyon on WP1.5 meeting Status source term + SGTR Johan Carlsson.
Bologna on 28 May 2008 – IP EUROTRANS WP1.51 IE - Institute for Energy Petten - The Netherlands
WP 1.5 Progress Meeting ENEA – Bologna, Italy, May 28-30, 2008 FPN-FISNUC / Bologna EUROTRANS – DM1 Analysis of EFIT Unprotected Accidental Transients.
KIT – Universität des Landes Baden-Württemberg und nationales Forschungszentrum in der Helmholtz-Gemeinschaft Karlsruhe Institute of Technology, Germany.
Investigation into the Viability of a Passively Active Decay Heat Removal System In ALLEGRO Laura Carroll, Graduate Physicist Physics & Licensing Team,
Lead Technology Task 6.2 Materials for mechanical pump for HLM reactors M. Tarantino – ENEA Work Package Meeting – ENEA Bologna, November 17th, 2010.
Argonne National Laboratory 2007 RELAP5 International User’s Seminar
[T6.4] Assessment of damping pressure wave inside SG Technical meeting – KIT - Karlsruhe, 22/11/2012 A. Del Nevo, A. Ciampichetti Presented by Mariano.
Thermal hydraulic analysis of ALFRED by RELAP5 code & by SIMMER code G. Barone, N. Forgione, A. Pesetti, R. Lo Frano CIRTEN Consorzio Interuniversitario.
Pro-Science 4 th International Conference of Hydrogen Safety, September 12-14, 2011, SAN FRANCISCO, USA EXPERIMENTAL STUDY OF IGNITED UNSTEADY HYDROGEN.
LEADER, Task 5.5 ETDR Transient Analyses with SPECTRA Code LEADER Project JRC, Petten, February 26, 2013 M.M. Stempniewicz NRG-22694/
Analyses of representative DEC events of the ETDR
Lead Technology Task 6.2 Materials for mechanical pump for HLM reactors M. Tarantino, I. Di Piazza, P. Gaggini Work Package Meeting Karlsruhe, November.
LBE-Water interaction in LIFUS V facility under different operating conditions A. Ciampichetti, D. Bernardi - ENEA T. Cadiou - CEA N. Forgione – Università.
Thermal Model of MEMS Thruster Apurva Varia Propulsion Branch Code 597.
International Centre for Theoretical Physics (ICTP)
Analysis of the SGTR accident for LFR by SIMMER code Nicola Forgione CIRTEN Consorzio Interuniversitario per la Ricerca Tecnologica Nucleare UNIVERSITA’
Nuclear Thermal Hydraulic System Experiment
Development of a RELAP5-3D thermal-hydraulic model for a Gas Cooled Fast Reactor D. Castelliti, C. Parisi, G. M. Galassi, N. Cerullo (San Piero A Grado.
KIT – University of the State of Baden-Wuerttemberg and National Research Center of the Helmholtz Association Institute for Neutron Physics and Reactor.
Safety Analysis Results of the DEC Transients of ALFRED LEADER Lead-cooled European Advanced DEmonstration Reactor G. Bandini (ENEA), E. Bubelis, M. Schikorr.
1 Kaspar Kööp, Marti Jeltsov Division of Nuclear Power Safety Royal Institute of Technology (KTH) Stockholm, Sweden LEADER 4 th WP5 MEETING, Karlsruhe.
Please insert a figure in the master transparency. KIT – University of the State of Baden-Wuerttemberg and National Research Center of the Helmholtz Association.
Experimental and numerical studies on the bonfire test of high- pressure hydrogen storage vessels Prof. Jinyang Zheng Institute of Process Equipment, Zhejiang.
KIT – University of the State of Baden-Wuerttemberg and National Research Center of the Helmholtz Association Institute for Neutron Physics and Reactor.
Simulations of Coupled Core and Steam Generator Dynamics (Contribution to Task 4.4: “Preliminary definition of the Control Architecture” Status Report)
LEADER Project Analysis of Representative DBC Events of the ETDR with RELAP5 and CATHARE Giacomino Bandini - ENEA/Bologna Genevieve Geffraye – CEA/Grenoble.
Analysis of Representative DEC Events of the ETDR with RELAP5 LEADER Project: Task 5.5 G. Bandini - ENEA/Bologna LEADER 5 th WP5 Meeting JRC-IET, Petten,
ERMSAR 2012, Cologne March 21 – 23, ON THE ROLE OF VOID ON STEAM EXPLOSION LOADS.
KIT – University of the State of Baden-Wuerttemberg and National Research Center of the Helmholtz Association Institute for Neutron Physics and Reactor.
ERMSAR 2012, Cologne March 21 – 23, 2012 Experimental and computational studies of the coolability of heap-like and cylindrical debris beds E. Takasuo,
KIT TOWN OFFICE OSTENDORFHAUS Karlsruhe, 21 st November 2012 CIRTEN Consorzio universitario per la ricerca tecnologica nucleare Antonio Cammi, Stefano.
IHM/ KIT/ Campus Nord 1 | Georg Müller | LEADER Bologna November 17, 2010 LEADER WP6 AGENDA Bologna, November 17th, 2010 ENEA, Aula Magna 14.00Agenda (G.
Institute of Safety Research Member Institution of the Scientific Association Gottfried Wilhelm Leibniz DYN3D/ATHLET AND ANSYS CFX CALCULATIONS OF THE.
ERMSAR 2012, Cologne March 21 – 23, 2012 OECD Benchmark Exercise on the TMI-2 Plant: Analysis of an Alternative Severe Accident Scenario G. Bandini (ENEA),
Italian National Agency for New Technologies, Energy and Environment Advanced Physics Technology Division Via Martiri di Monte Sole 4, Bologna, Italy.
KIT – University of the State of Baden-Wuerttemberg and National Research Center of the Helmholtz Association Institute for Neutron Physics and Reactor.
EUROTRANS – DM1 Preliminary Transient Analysis for EFIT Design WP5.1 Progress Meeting AREVA / Lyon, October 10-11, 2006 G. Bandini, P. Meloni, M. Polidori.
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 Post-test calculations of CERES experiments using ASTEC code Lajos Tarczal 1, Gabor Lajtha 2 1 Paks Nuclear Power.
Duy Phan, EN-STI-RBS. Description of the hazards  An Oxygen Deficiency Hazard (ODH) exists when the concentration of O2 ≤ 19.5 % (by volume)  Cold burns.
November 19th 2010, Bologna LEADER 1 1st LEADER PCC MEETING WP4 PLANT OPERATION, INSTRUMENTATION, CONTROL AND PROTECTION SYSTEM DESIGN.
Nuclear Battery Battery.  Reactor –Core Metallic fuel core (U-10%Zr) –Reactivity control Movable reflectors –Shutdown system Shutdown rod and reflectors.
KIT – University of the State of Baden-Wuerttemberg and National Research Center of the Helmholtz Association Institute for Neutron Physics and Reactor.
A.Borovoi, S.Bogatov, V.Chudanov, V.Strizhov
Session Name: Lessons Learned from Mega Projects
Egyptian Atomic Energy Authority (EAEA), Egypt
Presentation transcript:

EUROTRANS – DM1 ENEA Activities on EFIT Safety Analysis ENEA – FIS/NUC Bologna - Italy WP5.1 Progress Meeting Tractebel / Brussels, March 17, 2006 G. Bandini, P. Meloni, M. Polidori

OUTLINE Planned Activities on EFIT Safety Analysis Transient Analysis with RELAP5/PARCS Use of SIMMER-III in MEGAPIE Safety Study and DM4 - DEMETRA SGTR Analysis with SIMMER-III Preliminary SIMMER-III Results

ENEA Activities on EFIT Safety Analysis Analysis of DBC and DEC transients with RELAP5/ PARCS coupled code Analysis of the SGTR and water-lead interaction with SIMMER-III code

Transient Analysis with RELAP5/PARCS Planned Approach Capability to treat global system behavior coupled with dynamic core response in transient conditions Investigation of whole spectrum of accidental DBC scenarios and DEC conditions (no severe accidents) Main differences respect to PDS-XADS to address code upgrading and activity planning: Lead instead of LBE as coolant Large positive reactivity potentials without prompt Doppler Preliminary investigation of safety issues to support core design

Transient Analysis with RELAP5/PARCS Completed and in Progress Activity Inplementation of Lead thermodynamics and physics properties in the last RELAP version MOD3.3 (capable to be coupled with most recent PARCS versions) Modification of v2.4 PARCS version to treat external source (hexagonal geometry, multi-group energy description) First coupled calculations and modelling of EFIT core (preliminary design) in progress

Use of SIMMER-III in MEGAPIE Safety Study Calculations of LBE-Water Interaction Accident for MEGAPIE Comparison with FZK calculation with MATTINA code SIMMER-IIIMATTINA

Validation of SIMMER-III on JAERI Experiments LBE-Water Interaction Test SIMMER-III and Test result comparison (vapor volume)

Use of SIMMER-III in DM4-DEMETRA Lead-Water interaction experiments will be performed in the Facilities (LIFUS and/or CIRCE) of ENEA/Brasimone site SIMMER-III code will be used in pre- and post-test analysis of these experiments Qualification of SIMMER-III models in connection with these experiments is proposed by ENEA in close cooperation with the University of Pise Based on the results of this work and eventual code model limits some model development work could be envisaged and proposed ENEA asks for the agreement by the SIMMER-III development team (JNC, FZK and CEA) to perform this task in close cooperation with the University of Pise (under responsibility of ENEA)

Analysis SGTR Accident in EFIT Preliminary SIMMER-III Calculations Use of a simplified 2-D cylindrical geometry Boundary conditions according to EFIT ANSALDO design Stagnant lead inside the vessel Lead  liquid fuel, Water  coolant in SIMMER-III lead-water interaction simulation 1 to 5 steam generator tube rupture

EFIT Design SIMMER-III Modelling Simplified R-Z Geometry (29 x 41) R Z

SGTR Accident in EFIT Simplified Assumptions in SIMMER-III Calculations Reactor Vessel Lead mass = 1850 tons (LBE properties with T melting = 328 °C) Lead temperature = 400 °C Cover gas volume = 41 m 3 (T = 400 °C, P = 1 Bar) Steam Generator Tube inside diameter = 14.2 mm Liquid mass = 31.1 kg; steam mass = 25.3 kg Volume = 0.32 m 3 ; void fraction = 84.7% Pressure = 140 Bar; Temperature = 335 °C Tube Rupture (1 and 5 SG tubes) Downwards flow at the heat hexchanger bottom Mass flowrate (1 tube) = 1.2 – 1.6 kg/s (steam and liquid mixture)

SG Break Mass Flowrate

Material Fractions 1 Tube Rupture Time = 0 – 30 s 0.1 s 1 s 3 s10 s 30 s

Material Fractions 5 Tubes Rupture Time = 0 – 30 s 0.1 s 1 s 3 s10 s 30 s

System Pressure 1 Tube Rupture t = 30 s

System Pressure 5 Tubes Rupture t = 30 s

1 to 5 SG Tube Rupture Comparison s

Main Conclusions from SGTR Analysis More suitable geometry must be chosen to model the SGTR in EFIT reactor with the SIMMER code (2-D or 3-D ?) Boundary conditions are still uncertain Preliminary calculations show that steam explosion effects are not of concern in the SIMMER-III evaluation Fast vapour expansion outside the break causes a significant movement of lead mass that impacts onto the vessel upper structures An almost linear increase of the cover gas pressure is computed by SIMMER-III in the time frame of tens of seconds