FRAPCON-3/FRAPTRAN APPLICATIONS Unit of Nuclear Safety Research

Slides:



Advertisements
Similar presentations
The PMBR steady-state and Coupled kinetics core thermal-hydraulics benchmark test problems PBMR (Pty) Ltd. – NRG – Penn State Univ. – Purdeu Univ. - INL.
Advertisements

NEEP 541 Design of Irradiated Structures Fall 2002 Jake Blanchard.
Improvements on FRAPCON3 and FRAPTRAN Mechanical Modelling Arttu Knuutila, Seppo Kelppe SAFIR-PUOLIVÄLISEMINAARI
1 Summary Slides on FNST Top-level Technical Issues and on FNSF objectives, requirements and R&D Presented at FNST Meeting, UCLA August 18-20, 2009 Mohamed.
Algorithm for Fast Statistical Timing Analysis Jakob Salzmann, Frank Sill, Dirk Timmermann SOC 2007, Nov ‘07, Tampere, Finland Institute of Applied Microelectronics.
FRAPCON/FRAPTRAN Code Application NRC Office of Research
Nuclear Safety Research Unit FRAPCON/FRAPTRAN users group meting Manchester (UK), CIEMAT ACTIVITIES on FRAPCON/FRAPTRAN APPLICATIONS ( )
Dynamic Response to Pulsed Beam Operation in Accelerator Driven Subcritical Reactors Ali Ahmad Supervisor: Dr Geoff Parks University Nuclear Technology.
First Wall Heat Loads Mike Ulrickson November 15, 2014.
EMERALD1: A Systematic Study of Cross Section Library Based Discrepancies in LWR Criticality Calculations Jaakko Leppänen Technical Research Centre of.
Pacific Northwest National Laboratory
UTILIZATION OF THE FRAPCON CODE IN BRAZIL FOR REGULATORIES MATTERS Brazilian Nuclear Energy CommisionBrazilian Nuclear Energy Commision Auro Pontedeiro.
Outlook for the Requirements of the Nuclear Power Plant Irradiation Test in China SONG DANRONG Nuclear Power Institute of China.
October 25-27, th International QUENCH Workshop 1 Top Flooding Experiments and Modeling Estelle Brunet-Thibault (EDF), Serge Marguet (EDF)
Reliability Prediction of a Return Thermal Expansion Joint O. Habahbeh*, D. Aidun**, P. Marzocca** * Mechatronics Engineering Dept., University of Jordan,
Specimen Size Effects in the Determination of Nuclear Grade Graphite Thermal Diffusivity ASTM D02F000 Symposium on Graphite Testing for Nuclear.
VG.1 SCWR Fuel Rod Design Requirements Design Limits Input for Performance Evaluations H. Garkisch, Westinghouse Electric Co.
1 FRAPCON Statistical Package FRAPCON/FRAPTRAN Users Group Meeting September 7, 2012 Paul Clifford Division of Safety Systems Office of Nuclear Reactor.
Power Extraction Research Using a Full Fusion Nuclear Environment G. L. Yoder, Jr. Y. K. M. Peng Oak Ridge National Laboratory Oak Ridge, TN Presentation.
Fuel Behavior in Long-term Management of Spent Light-Water Reactor Fuel International Conference on Management of Spent Fuel from Nuclear Power Reactors.
IRSN Views on the R & D Needs and Strategy Towards a Revision of LOCA Acceptance Criteria in France Michel SCHWARZ, Claude GRANDJEAN, François BARRE,
U.S.NRC 2014 FRAPCON/FRAPTRAN Code Applications and Developments
Thermal hydraulic analysis of ALFRED by RELAP5 code & by SIMMER code G. Barone, N. Forgione, A. Pesetti, R. Lo Frano CIRTEN Consorzio Interuniversitario.
Nuclear Research Institute Řež plc 1 DEVELOPMENT OF RELAP5-3D MODEL FOR VVER-440 REACTOR 2010 RELAP5 International User’s Seminar West Yellowstone, Montana.
Thermal Analysis of Spent LWR Fuel Casks Under Normal and Accident Conditions Miles Greiner University of Nevada, Reno Systems Analysis Technical Guidance.
Study of a new high power spallation target concept
Distributions of fission products on PCI in spent PWR fuels using EPMA
1 VI Single-wall Beam Pipe tests M.OlceseJ.Thadome (with the help of beam pipe group and Michel Bosteels’ cooling group) TMB July 18th 2002.
Completion of Water-Cooled Backup Study Eric Pitcher TAC-10 November 5, 2014.
Nuclear Fuels Storage & Transportation Planning Project Office of Fuel Cycle Technologies Nuclear Energy Criticality Safety Assessment for As-loaded Spent.
Fire Safety in Nuclear Power Plants and Modeling Fire in a Generic EDG Room by COMPBRN III M. B. Öztemiz, Ş. Ergün Hacettepe University Nuclear Engineering.
FEDERAL STATE UNITARY ENTERPRISE Alexandrov Research Institute of Technology SOSNOVY BOR, RUSSIA FEDERAL STATE UNITARY ENTERPRISE Alexandrov Research Institute.
Nuclear Safety Research Unit Vienna (Austria), IAEA meeting Evaluation of creep during dry storage in low and high burnup fuels F. Feria,
FRAPCON/FRAPTRAN Users Group Meeting: Recent Code Updates and Future Plans Ken Geelhood Walter Luscher Carl Beyer Pacific Northwest National Laboratory.
KAIST Hee Cheon NO Nuclear System/Hydrogen Lab.
Probabilistic Design Systems (PDS) Chapter Seven.
Nuclear Safety Research Unit FRAPCON/FRAPTRAN USERS GROUP MEETING Charlotte, NC (USA), CIEMAT ACTIVITIES on FRAPCON/FRAPTRAN APPLICATIONS ( )
Oxygen Potential in High Burnup LWR Fuel using Themochimica in MOOSE/BISON Theodore M. Besmann.
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.
IMPACT 4 November 20044th IMPACT Workshop - Zaragoza1 Investigation of extreme flood Processes and uncertainty Model uncertainty How uncertain are your.
1 Demonstration Test Program for Long–term Dry Storage of PWR Spent Fuel 2 June 2010 M. Yamamoto, The Japan Atomic Power Company The Kansai Electric Power.
Extented scope and objectives
Validation of Traditional and Novel Core Thermal-Hydraulic Modeling and Simulation Tools Issues in Validation Benchmarks: NEA OECD/US NRC NUPEC BWR Full-size.
Panel Discussion: Discussion on Trends in Multi-Physics Simulation
Measurement of Thermal Gap Conductance Using the Laser Flash Method
Characteristics of fuel rod behaviour during LOCA
User Group Meeting | 2015 | Zurich, CH
Recent FRAPCON and FRAPTRAN activity at VTT
Sandrine BOUTIN – Stéphanie GRAFF – Aude TAISNE – Olivier DUBOIS
Vattenfall’s use of FRAPCON for PWR cycle-specific verification
Monte Carlo Simulation Managing uncertainty in complex environments.
Probabilistic Methods: Theory and Application to Human Anatomy
Jordan University of Science and Technology
User Group Meeting | 2016 | Boise, Idaho, USA
User Group Meeting | 2017 | Jeju Island, Korea
Ken Geelhood Walter Luscher
2017 FRAPCON AND FRAPTRAN USER GROUP MEETNG
SAFETY AND SITTING ASSESSMENT FOR NPPs DEPLOYMENT IN INDONESIA
Data transfer between codes
Adaptation of FRAPTRAN 2. 0 to VVER Fuel FRAP
VICTOR HUGO SANCHEZ ESPINOZA and I. GÓMEZ-GARCÍA-TORAÑO
2015 FRAPCON AND FRAPTRAN USER GROUP MEETNG
Recent FRAPCON and FRAPTRAN activity at VTT
IRSN work and perspectives
Recent IRSN work on FRAPCON-3
FRAPCON/FRAPTRAN activity at VTT
Advances in predictive thermo-mechanical modelling for the JET divertor experimental interpretation, improved protection, and reliable operation D. Iglesias,
NUMERICAL STUDY OF IN-VESSEL CORIUM RETENTION IN A BWR REACTOR M
THE EXPECTATIONS OF THE FUEL VENDOR IN THE FIELD OF REACTOR MATERIAL SCIENCE OF NUCLEAR FUEL. THE RESULTS OF THE COOPERATION AND MATERIAL SCIENCE ASPECTS.
«ROSATOM» State Atomic Energy Corporation
Presentation transcript:

FRAPCON-3/FRAPTRAN APPLICATIONS Unit of Nuclear Safety Research CIEMAT ACTIVITIES on FRAPCON-3/FRAPTRAN APPLICATIONS (2014-2015) Unit of Nuclear Safety Research Division of Nuclear Fission CIEMAT-Madrid Spain

MAIN ACTIVITIES UA Steady state (CNAT) Power ramp (NEA) FRAPCON-3 FRPCN-3xt RIA (CSN/NEA) LOCA (CSN/HALDEN) FRAPTRAN Dry storage (ENRESA/ESCP) 2

STEADY STATE POWER RAMP Activity: Verification of safety analyses on PWR fuel performance (Trillo NPP) Code: FRAPCON-3.5 Outcomes: ongoing POWER RAMP Activity: Assessment of codes to simulate PCMI during ramps (NEA benchmark) Code: FRAPCON-3.5 Outcomes: ongoing 3

RIA Activity: Assessment of codes to simulate RIAs (NEA bnchmrk II) Code: FRAPTRAN-1.5 10 postulated cases - fresh fuel Remarks: Special attention should be paid to clad-to-coolant heat transfer model, particularly for BWR conditions Considering the large cladding temperature gradient under RIA conditions the validity of the thin wall approach used in the mechanical module would be worth to be revised The results highlight that the gap closure/reopening has strong influence in thermal-mechanical predictions. For instance, an unexpected fuel relocation contribution of the initial gap was detected and corrected by the NRC 4

LOCA Activity: Assessment of codes to simulate LOCAs (Halden tests) Code: FRAPCON-3.5+FRAPTRAN-1.5 (v1.4 also used in PWRs) IFA-650.5, .3, .10 (PWR) & IFA-650.7, .12 (BWR) Preliminary remarks: Outer cladding temperature shows moderate deviations from data (HTCs were imposed) PIE data are scarce to assess oxide modeling (protective and non-protective options) Cladding elongation at failure time shows substantial deviations from data in v1.5 (BALON2 modifications) 5

DRY STORAGE Activity: Extension of FRAPCON-3.5 to dry storage conditions (ENRESA) 6

DRY STORAGE Focus: Cladding performance – Vertical cask FRAPCON-3xt can predict long storage cladding T If DBTT is known, t-to-DBT estimations can be done 7

Uncertainty analysis. RIA Activity: Impact of steady state uncertainties on RIA modeling (CSN) Code: FRAPCON-3.5 (→SCANAIR) Scenario: Realistic case - Irradiated fuel (PWR, 68.5 GWd/tU) - Power pulse (99 cal/g, 32 ms) Sensitivity analysis Order statistics Failure prediction can be improved by: Enhancing FRAPCON-3 models affecting oxide thickness prediction, specially the oxide conductivity model Ensuring an accurate characterization of the gap width at the beginning of the transient Top Fuel 2015 8

Uncertainty analysis. Dry storage Activity: Uncertainty calculation of PEOL as DS initial condition (ENRESA/ESCP) Code: FRAPCON-3.5 Scenario: Zry-4 fuel rod (65 GWd/tU) UA: Monte Carlo based on deterministic reduction NUREG-1754 If uncertainties were accounted for, it would be difficult to analyse the power history effect Upper bound predictions would allow estimating conservative stresses at DS onset Top Fuel 2015 9

THANK YOU FOR YOUR ATTENTION 10

RIA Cases 5 and 7: Fresh fuel - Triangular power pulse (127 cal/g , 30 ms) 11

LOCA PWR (61 GWd/tU) 12