NSE Nuclear Science & Engineering at MIT science : systems : society Better reactors grow from better simulations Emilio Baglietto emiliob@mit.edu Massachusetts web.mit.edu/newsoffice/2012/baglietto-better-reactors.htm l Institute of Technology
An Industrial/Research/Academic view Wearing multiple hats: Massachusetts Assistant Professor of Nuclear Science and Institute of Engineering, Massachusetts Institute of Technology. Technology Deputy Lead TH Methods Focus Area, CASL – a US Department of Energy HUB. Nuclear Industry Sector Specialist CD-adapco. Member of NQA-1 Software Subcommittee. Disclaimer: the following slides are intended for general discussion. They represent the personal view of the author and not that of MIT, CASL or the ASME NQA-1 Software Subcommittee. STAR Chinese Conference 2013 Better reactors grow from better simulations
Contents Nuclear Industry Competitiveness CFD for Nuclear Reactor Design Leveraging the research/academia efforts Computational Microscopes Multi-scale Applications CFD as Multi-physics platform CFD for Advanced Reactor Concepts Fast Reactors Fuel VHTRs – virtual experiments Extreme Heat Removal STAR Chinese Conference 2013 Better reactors grow from better simulations
CASL: The Consortium for Advanced Simulation of Light Water Reactors A DOE Energy Innovation Hub for Modeling & Simulation of Nuclear Reactors Task 1: Develop computer models that simulate nuclear power plant operations, forming a “virtual reactor” for the predictive simulation of light water reactors. Task 2: Use computer models to reduce capital and operating costs per unit of energy, …… STAR Chinese Conference 2013 4 Better reactors grow from better simulations
Virtual Environment for Reactor Applications VERA Neutronics Thermo- Thermal-Hydraulics Mechanics XSProc COBRA-TF Baseline Denovo Hydra-TH VABOC Chemistry Drekar MPACT BOA MAMBA PEREGRINE STAR-CCM+ DeCART ANC9 VIPRE-W Geometry / Mesh / DataTransferKit (DTK) LIME Trilinos DAKOTA MOOSE Common RELAP5 Input system front-end Emilio Baglietto - Nuclear Science & Engineering at MIT
What does workstation mean? VERA platform options laptops, workstations, clusters, HPC systems (current vs. future) What does workstation mean? you can get a 1.4 TF/s desk-side box with up to 512 GB, 16 CPU cores and ~900 GPU cores today Date 1984 1997 2000 2007 2011 Cost/GFLOPS $15million $30,000 $640 $48 $1.80 OAK RIDGE, Tenn., Nov. 12, 2012 — The DOE Oak Ridge National Laboratory is again home to the most powerful computer in the world – Titan is a Cray XK7 system that contains 18,688 nodes, capable of a theoretical peak speed of 27 petaflops Emilio Baglietto - Nuclear Science & Engineering at MIT
4-Loop Westinghouse PWR Multi-Physics Model Development RPV ID 173”, 193/4 Fuel Assemblies,13,944 fuel rods (fuel pellets, helium gap), 434 spacers, 148,224 mixing vanes; 1.2 billion cells Drawings CAD Model CFD Model Emilio Baglietto - Nuclear Science & Engineering at MIT
4-Loop Westinghouse PWR Multi-Physics Model Development RPV ID 173”, 193/4 Fuel Assemblies,13,944 fuel rods (fuel pellets, helium gap), 434 spacers, 148,224 mixing vanes; 1.2 billion cells CFD Model Results Mesh Emilio Baglietto - Nuclear Science & Engineering at MIT
A “Typical” Multi -Scale Problem Full-core performance is affected by localized phenomena Model 1 Model 2 • Local T&H conditions such as pressure, velocity, cross flow magnitude can be used to address challenge problems: o GTRF o FAD o Debris flow and blockage • The design TH questions under normal operating and accident conditions such as: o Lower plenum flow anomaly o Core inlet flow mal-distribution o Pressure drop o Turbulence mixing coefficients input to channel code o Lift force o Cross flow between fuel assemblies o Bypass flow • The local low information can be used as boundary conditions for micro scale models. Emilio Baglietto - Nuclear Science & Engineering at MIT
Thermal Hydraulics & Neutronics Coupling CFD + Neutronics full depletion cycle simulation: 14 state points, total time required for a complete depletion cycle: 44 hours on 1028 cores . ANC power 150MW*DAYS Full Power 2000MW*DAYS 1000MW*DAYS 44 hours /depletion-cycle proves that high fidelity CFD & Neutronics coupling is practical for engineering design for finalizing core design. The results will provide hot spot, boiling areas for CILC and crud simulation, fuel center line temperature, peak cladding temperature, and cross flow for GTRF. Emilio Baglietto - Nuclear Science & Engineering at MIT
STAR-CCM+ Platform for Multiphysics High Fidelity T-H / Neutronics / CRUD / Chemistry Modeling Petrov, V., Kendrick, B., Walter, D., Manera, A., Impact of fluid-dynamic 3D spatial effects on the prediction of crud deposition in a 4x4 PWR sub-assembly - NURETH15, 2013 Emilio Baglietto - Nuclear Science & Engineering at MIT
STAR-CCM+ Platform for Multiphysics High Fidelity T-H / Neutronics / CRUD / Chemistry Modeling Petrov, V., Kendrick, B., Walter, D., Manera- NURETH15, 2013 Emilio Baglietto - Nuclear Science & Engineering at MIT
boiling heat transfer void fraction DNB Multiphase CFD … better physical understanding Emilio Baglietto - Nuclear Science & Engineering at MIT
Improved Spacers Design CFD Predictions of DNB CFD–based CHF modeling development being performed by Westinghouse Nuclear Fuel. 5x5 test bundle PWR experiment from the ODEN CHF test facility were modeled in CFD using the latest 2-phase boiling model. Excellent trend agreement in CHF predictions. Novel understanding of fundamental physics allows improving the CHF performance. J. Yan, et al - Evaluating Spacer Grid CHF Performance by High Fidelity 2-Phase Flow Modeling – TOPFUEL2013 16 STAR Chinese Conference 2013 Better reactors grow from better simulations
Improved Spacers Design 17 J. Yan, et al - Evaluating Spacer Grid CHF Performance by High Fidelity 2-Phase Flow Modeling – TOPFUEL2013 STAR Chinese Conference 2013 Better reactors grow from better simulations
RCIC SYSTEM 22 MO MO Turbine HO 70 HOURS stop valve #2 HO RCIC Control valve TIME 20 HOURS #3 RCIC TIME M. Pellegrini, M. Naitoh, E. Baglietto
UNITS 2 & 3: PCV PRESSURE 23 EARTHQUAKE U N I T 3 3/11 14:46 0.6 Primary containment vessel pressure (MPa [abs]) 0.4 0.2 U N I T 2 0 3/11 3/12 3/12 3/13 3/13 12:00 0:00 12:00 0:00 12:00 Date/time M. Pellegrini, M. Naitoh, E. Baglietto
SPARGER MAIN DIFFERENCES 24 D=0.010 m U N I T 2 U N I T 3 0.033 m VERTICAL JET HORIZONTAL 0.036 m JETS D = 0.025 m 0.065 m 0.680 m 1.275 m 2577 mm 0.283 m M. Pellegrini, M. Naitoh, E. Baglietto
1F3 GEOMETRY 25 Detail of holes mesh size Region A size = 1 mm Region B size = 2 mm Pool pressure boundary Region B ~ 8 m sparger Elements size in the pool = 0.1~0.2 m M. Pellegrini, M. Naitoh, E. Baglietto
1F3 TEMPERATURE IN THE SPARGER 26 steam flow 2 seconds real time Region A ~ 3.0 m Region B T pool = 30°C Large water head creates differences between mass flow rate between holes in the vertical direction M. Pellegrini, M. Naitoh, E. Baglietto
POOLEX STB-28-4 EXPERIMENT 27 steam inlet facility pool detail sketch 219.1 mm 380 mm Experimental results • Large visible chugging phenomenon • Bubble collapse time = 80 ms T pool = 62 ° C • Bubble diameter = 380 mm Steam Mass Flux = 8 kg/m 2 s • Collapse speed = 3 m/s M. Pellegrini, M. Naitoh, E. Baglietto
PRELIMINARY RESULTS: CHUGGING 28 0.3 kg/s Flow enters the pool. Large turbulence is created, increased condensation volume fraction 1.00 CONDENSATION MASS TRANSFER 0.75 0.50 0.25 0.00 0.3 kg/s PIPE MOUTH M. Pellegrini, M. Naitoh, E. Baglietto
FIRST BUBBLE ANALYSIS GROWTH 29 STB-28-4 MEASUREMENTS Animation of the first bubble STAR-CCM+ RESULTS • Chugging phenomenon can be recreated only for the first bubble • Bubble collapse velocity and phenomenon stability is highly dependent on the modeling assumptions • More physical investigation and sensitivity analysis is required M. Pellegrini, M. Naitoh, E. Baglietto
PVP2012-78491: CFD ANALYSES OF THE TN-24P PWR SPENT FUEL STORAGE CASK R. A. Brewster, E. Baglietto, E. Volpenhein, C. Bajwa Spent Fuel Simulations Emilio Baglietto - Nuclear Science & Engineering at MIT
Dominantly Polyhedral • The overall mesh consists of Cells about 18 million cells Porous blocks meshed using trimmed hexa • Of these, approximately 2 million are in the fluid domain STAR Chinese Conference 2013 Better reactors grow from better simulations
Example of Analysis Results Basket Temperatures Cask Temperatures Total power dissipation in cask = 20,640 Watts STAR Chinese Conference 2013 Better reactors grow from better simulations
Recommend
More recommend
