fzd theory seminar series cfd simulations for single and
TRANSCRIPT
Institute of Safety Research � FWSS � Dr. Thomas Höhne � www.fzd.de � 19.03.2010 1
Nuclear Safety Research
Thomas HThomas Hööhnehne
FZDFZDDresdenDresden--Rossendorf, GermanyRossendorf, Germany
CFD simulations for CFD simulations for single and multisingle and multi--phase phase flowsflows
FZD Theory Seminar SeriesFZD Theory Seminar Series
Institute of Safety Research � FWSS � Dr. Thomas Höhne � www.fzd.de � 19.03.2010 2
Nuclear Safety ResearchWhat is CFD?What is CFD?
� CFD (Computational Fluid Dynamics) is the simulation of fluids
engineering systems using modeling (mathematical physical
problem formulation) and numerical methods (discretization
methods, solvers, numerical parameters, and grid generations,
etc.)
� CFD made possible by the advent of digital computer and
advancing with improvements of computer resources (500
Floating Point Operations per Second (flops), 1947
�1 Petaflops, 2009)
Jugene am FZ Jülich
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Nuclear Safety ResearchWhere is CFD used?Where is CFD used?
Where is CFD used?
– Aerospace
– Automotive
– Biomedical
– Chemical
Processing
– HVAC
– Hydraulics
– Marine
– Oil & Gas
– Power
Generation
– Sports
Aerospace
Power Generation
Automotive
Sports
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Nuclear Safety ResearchCFD ModelingCFD Modeling
�CFD Modeling is the mathematical physics problem formulation in the form of Partial Differential
Equations (PDEs) with appropriate boundary conditions and initial conditions.
�Modeling includes:
1. Geometry and domain
2. Coordinates
3. Governing equations
4. Flow conditions
5. Initial and boundary conditions
6. Selection of models for different applications
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Nuclear Safety ResearchCFD Methods - Definition
• Basis � Continuum
mechanics
• Conservation laws for– Mass
– Momentum
– Energy
– Species concentration
– …
• Equation characteristics– Geometry independent
– Galilean invariant
– Boundary conditions
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Nuclear Safety ResearchCFD & System Codes
• System codes
• Geometry & flow approximation: 1-D
• Less computing time
• Less computer memory
• Larger assemblies �whole systems
• Increased empirical input
• Application dependent
• CFD codes
• Geometry & flow field resolution
• High computing times
• Large computer memory
• Smaller assemblies �
components
• Reduced empirical input
• Application ‘independent’
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Nuclear Safety Research
Geometry ModellingGeometry Modelling
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Nuclear Safety ResearchGeometry Geometry ModellingModelling
� Simple geometries can be easily created by few geometric parameters (e.g. circular pipe)
� Complex geometries must be created by importing the database of the geometry(e.g. airfoil) into commercial software
� Typical approaches
�Geometry approximation
�CAD/CAE integration:
use of industry standards
such as Parasolid, ACIS,
STEP, or IGES, etc.
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Nuclear Safety ResearchGrid Generation
• Geometry & grid generation:– Time-consuming
– Labour-intensive � expensive
• CFD result quality &
computing times � strongfunction of grid quality
• Grid generation process:– High intellectual & cognitive
demands �
– Difficult to ‚automate‘
• ‚Critical Path‘ for closer
integration of CFD in designand optimization procedures
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Nuclear Safety ResearchGrid Requirements
• Grid widths sufficiently small
� Discretisation errorssufficiently small (accuracy)
• Grid widths sufficiently large
� Computer memory & computing time limitations
• Grid point arrangement �Minimisation of discretisation
errors
• Discretisation errors: Difference between
numerical and exact solution � infinitely fine grid
h h exe f f= −
-0,300
-0,200
-0,100
0,000
0,100
0,200
0,300
0 5 10 15 20 25 30 35 40
x/H, -
Skin
fri
cti
on
co
eff
icie
nt,
-
Grid 1
Grid 2
Grid 3
Grid 4
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Nuclear Safety ResearchElement Types
• Common 3-D element types:
PyramidPrismTetrahedron (tet)Hexahedron (hex)
• General polyhedra, …
• Difference between control volumes & elements
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Nuclear Safety ResearchElements & Control Volumes
• “Cell-Centred”
• Element = Control volume
• “Vertex-Centred”
• Element-vertex-method
• Element � Control volume
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Nuclear Safety Research
Mathematical ModelsMathematical Models
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Nuclear Safety ResearchModeling (governing equations)Modeling (governing equations)
Navier-Stokes equations (3D in Cartesian coordinates)
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∂
∂+
∂
∂+
∂
∂+
∂
∂−=
∂
∂+
∂
∂+
∂
∂+
∂
∂2
2
2
2
2
2ˆ
z
u
y
u
x
u
x
p
z
uw
y
uv
x
uu
t
uµρρρρ
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∂
∂+
∂
∂+
∂
∂+
∂
∂−=
∂
∂+
∂
∂+
∂
∂+
∂
∂2
2
2
2
2
2ˆ
z
v
y
v
x
v
y
p
z
vw
y
vv
x
vu
t
vµρρρρ
( ) ( ) ( )0=
∂
∂+
∂
∂+
∂
∂+
∂
∂
z
w
y
v
x
u
t
ρρρρ
RTp ρ=
Convection Pressure gradient Viscous termsLocal
acceleration
Continuity equation
Equation of state
��
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∂
∂+
∂
∂+
∂
∂+
∂
∂−=
∂
∂+
∂
∂+
∂
∂+
∂
∂2
2
2
2
2
2ˆ
z
w
y
w
x
w
z
p
z
ww
y
wv
x
wu
t
wµρρρρ
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Nuclear Safety ResearchConservation Equation
( ) ( )j j
jF U F D S
t xρ ρ ρ
∂ ∂+ + =
∂ ∂
Concentration
Energy
Momentum
Mass
Variable F
1
jU
E
C
( )j ij ij iq P Uτ δ+ +
ij ijPτ δ+
0
jD
jJ
S
0
ig
i ig U
R
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Nuclear Safety ResearchCFD Solver
Numerical
Algorithms
Numerical
AlgorithmsComputer
Architecture
Computer
Architecture
Mathematical
Models
Mathematical
Models
CFD SolverCFD Solver
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Nuclear Safety ResearchMathematical Models
• 5 Conservation laws– 1 × Mass
– 3 × Momentum
– 1 × Energy
• 5 Unknowns– U, V, W, P, E
• Closed system– Laminar flows &
– Turbulent flows
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Nuclear Safety Research
TurbulenceTurbulence
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Nuclear Safety ResearchTurbulenceTurbulence
�Turbulent flows:� Three-dimensional
� Unsteady-state
� Irregular
� Large spectrum of length and time scales
�„Huge“ computational effort �
�Turbulence models� Statistical models
� …
� Scale-resolving models
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Nuclear Safety ResearchTubulence Spectrum
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Nuclear Safety ResearchTurbulenceTurbulence ParametrisationParametrisation
• Energy-containing large eddies– Velocity scale, Vc
– Length scale, Lc( )2 2 2
1 2 3
3 2
1
2
c
c
V k
k u u u
kL
ε
=
′ ′ ′= + +
=
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Nuclear Safety ResearchModelling Strategies
SASSolution controlled
DESGrid controlled
(U)RANSAllNone
LESSmallLarge
DNSNoneAll
ModelResolve
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Nuclear Safety ResearchURANS Equations
( )0
j
j
U
t x
ρρ ∂∂+ =
∂ ∂
( ) ( ) ( )i j i ij i
j
j
i j
U U U P
x
u
x
u
t x
ρ ρ τ ρ∂ ∂ ∂ +∂+ = −
∂
′−
∂ ∂
′
∂
jiij
j i
UU
x xτ µ
� �∂∂= − + ∂ ∂� �
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Nuclear Safety ResearchURANS: Eddy Viscosity Models
• Eddy viscosity:
t c cV Lµ ρ=
D�kk-�
2-Eqn
A & D�m�t1-Eqn
D� & �kSST
D�kk-�
A�mMixing length
0-Eqn
Algebraic or Diff.
LcVcNameClass
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Nuclear Safety ResearchTurbulence Turbulence ModelingModeling withwith RANS modelsRANS models
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Nuclear Safety ResearchNear Wall Turbulence Modeling
Standard Log-Law Wall
Functions
• The k-ε model uses log-law wall
functions to provide the
hydrodynamic wall shear stress.
• The near wall tangential velocity is
related to the wall shear stress by
means of a logarithmic function.
- where κ and C are constants
depending on wall roughness
Log-law Wall Function
Cyy += ++ )ln(1
κ
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Nuclear Safety ResearchScaleScale--resolvingresolving model model -- LESLES
Large eddies of the turbulence are computed and only the smallest eddies
are modeled.
� Filtering operation of the physical quantities which preserves only their
large scale components. Usually, the computational grid serves as a low
pass filter and only the subgrid scale turbulent phenomena are modeled
� Smagorinsky subgrid scale model; it is an eddy viscosity model, that is
based on the assumption, that the effect of the small scales eddies can be
accounted for by adding a contribution to the momentum diffusivity
( ) ijijSt SSC ⋅⋅⋅∆= 22
ν�
��
�+=
i
j
j
iij
x
U
x
US
∂∂
∂∂
21
The characteristic length scale ∆ refers to the filter width and corresponds to the mesh spacing. CS is the Smagorinsky constant (CS = 0.18), reduction
of the eddy viscosity near walls with Van Driest damping functions
rate-of-strain tensor
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Nuclear Safety ResearchTubulence Spectrum
Modeled URANS
DNS computed
LES computed LES modeled
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Nuclear Safety ResearchExamples of modeling (Turbulence)Examples of modeling (Turbulence)
LES, Re=105, Iso-surface of Q criterion (0.005)
for turbulent flow in a T-junction
URANS, Re=105, Iso-surface of Q criterion
(0.005) for turbulent flow in a T-junction
Visualization of flow structure by isosurfaces of Q-criteria - the value of Q is a measure for visualized scales
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Nuclear Safety Research
Multiphase FlowMultiphase Flow
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Nuclear Safety ResearchMulti-Phase Flow Simulation
• Euler-Lagrange:– Continuous ‚carrier‘ phase �
Euler
– Tracking of single particles or
particle groups
– Interaction with carrier phase
– Limited to disperse flows
• Euler-Euler:– Interpenetrating continua
– Phase indicator function
– Phase weighted averaging
– Additional unknowns �
consequence of averaging
– Empirical closure
– More ‚general‘ approach
Multi-Phase Flow CFD
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Nuclear Safety ResearchPhase Indicator Function
t
Mk
0
1
‘Phase sensor’
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Nuclear Safety ResearchMass Conservation Equation
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Nuclear Safety ResearchMomentum Conservation Equation
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Nuclear Safety ResearchMomentum Conservation Equation
Institute of Safety Research � FWSS � Dr. Thomas Höhne � www.fzd.de � 19.03.2010 36
Nuclear Safety Research
Numerical MethodsNumerical Methods
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Nuclear Safety ResearchCFD Solver: Elements
Discretization –
Solution domain
Discretization –
Equations
Equation coupling
Matrix solvers
Parallelisation
Model equations
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Nuclear Safety ResearchSegregated Solution
• Generic coupled system(e.g. velocities U and V):
• Segregated solution:
uu uv u
vu vv v
A A BU
A A BV
� � � �� �⋅ = � �� � � �
k
uu uv uCalculate A , A V , B k 1Solve for U +
k 1
vv vu vCalculate A , A U , B+k 1Solve for V +
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Nuclear Safety ResearchCoupled Solution 1
uu uv u
vu vv v
A A BU
A A BV
� � � �� �⋅ = � �� � � �
uu uv vu vv u vCalculate A , A , A , A , B , B k 1 k 1Solve for U ,V+ +
• Generic coupled system
(e.g. velocities U and V):
• Coupled solution:
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Nuclear Safety ResearchCoupled Solution 2
• Coupled solution of linear equation systems:
– The solution variables of all coupled equations are always on the
same time/iteration
– Avoid unphysical over- and undershoots
– Improved robustness:
• Coupling between velocity and pressure
• Coupling of velocity components for rotating systems
• Coupling of the species in a combustion calculation
• Coupling of different phases in a multiphase flow calculation
– More effort per iteration but less iteration required in order to reach
convergence
– 1 ‘big’ matrix instead of several ‘small’ matrices
• Increased memory requirements
– Allows larger time steps
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Nuclear Safety ResearchILU – The Smoother
11
11
11
11
A L U
• Incomplete Lower/Upper-Decomposition
– forward and backward substitution
– ILU factorisation only modifies the main diagonal
� efficient storage: original matrix + one nodal array
– tends toward a 1-D Trid-Diagonal Matrix Algorithm (TDMA) for
equations with very large coefficients
� well suited as smoother for multigrid solver
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Nuclear Safety Research
Segregated Coupled
Coupled Volume Fractions
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Nuclear Safety ResearchMatrix Solvers
• Objective:– Efficient solution of sparse
system
• Scalability
• Relative effort for 2-D-Poisson equation
8 sN log(N)Multigrid
5 minN1.25SSOR-PCG
0.5 hN1.5SOR, CG
2.5 hN2Gauss-Seidel
5 hN2Jacobi
24 hN2Gauss elimination(direct)
CPU-tOperation
Count Method
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Nuclear Safety Research
• Simple relaxation methods are
good at reducing error
components that have short
wavelengths with respect to the
grid spacing.
• In Multigrid, a hierarchy of grids is
constructed, each coarser than
the previous grid.
• Applying the simple relaxation
method to each grid results in a
reduction of all components of
error in the final solution.
The left side of the figure shows the grids; the right side shows the error components that are most effectively treated on that grid.
Algebraic Multi-Grid Method
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Nuclear Safety ResearchAlgebraic Multi-Grid Method
• Dynamic multigrid hierarchy
• Scalable parallelization
Fine grid
Coarsest grid
Coarse grid...
...
V-cycle W-cycle Others ...
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Nuclear Safety ResearchHigh performance computingHigh performance computing
• CFD computations are usually very expensive which requires
parallel high performance supercomputers with the use of multi-
block technique.
multi-block technique
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Nuclear Safety ResearchParallel Computing
• Single Program Multiple Data (SPMD):– Identical code @ all processors
– Communication between processors: PVM, MPI, …
• “Domain-Decomposition”
Inner node Cut element Core elementOverlap node
Original gridPartitioned grid
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Nuclear Safety Research
1.1.ExampleExample
CFD CFD Calculation of horizontal Calculation of horizontal
gas/liquid flow experimentsgas/liquid flow experiments
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Nuclear Safety ResearchIntroduction and motivationIntroduction and motivation
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Nuclear Safety ResearchHot leg and pressure chamberHot leg and pressure chamberH
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Vallee, C.; Deendarlianto,.; Beyer, M.; Lucas, D.; Carl, H.Journal of Engineering for Gas Turbines and Power - Transactions of the ASME 131(2009)2, 022905
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Nuclear Safety ResearchThe hot leg model: Types of experimentsThe hot leg model: Types of experiments
• Co-current flow experiments:
air inlet
water inlet
air
outlet
SG inlet chamber & separator
RPV
simulator
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ate
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Nuclear Safety ResearchExample of coExample of co--current flow experimentcurrent flow experimentH
ori
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nta
l A
ir/w
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r F
low
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ir/w
ate
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Nuclear Safety ResearchCFD simulation of twoCFD simulation of two--phase cophase co--current flowcurrent flow
• Boundary conditions:
– pressure: 3.14 bar
– temperature: 22.3 °C
– air flow rate: 0.036 kg/s
– water flow rate: 0.902 kg/s
• CFD modeling:
– Euler-Euler two fluid model
– interphase transfer model: mixture model using the AIAD model
– fluid dependent k-� turbulence
model with turbulence damping functions and automatic wall functions
experiment simulation
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Nuclear Safety Research
2. Example2. Example
Coolant MixingCoolant Mixing
(Boron Dilution Transients)(Boron Dilution Transients)
Co
ola
nt
Mix
ing
Co
ola
nt
Mix
ing
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Nuclear Safety Research
Basic PhenomenonBasic Phenomenon
Boron 10 = strong thermal
neutron absorber
� Used as boric acid solved in
the coolant of PWRs to
compensate excess reactivity
� inadvertent or unavoidable
decrease of boron
concentration (boron dilution)
might result in a reactivity
transient
� Power peak depends on
coolant mixing in cold leg,
downcomer lower plenum
� Density differences can
strongly influence the mixing
Steam Generator
Pressurizer
RPV
Main Coolant Pump
deborated slug
ECCS
Scheme of the primary circuitScheme of the primary circuit
NPP PhilipsburgNPP Philipsburg
Motivation Motivation –– Safety of Nuclear Power PlantsSafety of Nuclear Power PlantsC
oo
lan
t M
ixin
gC
oo
lan
t M
ixin
g
ReactorReactorPressurePressureVesselVessel
SteamSteamGeneratorGenerator
Main CoolantMain Coolant
PumpPump
DeboratedDeborated SlugSlug
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Nuclear Safety ResearchROCOM: ROCOM: ROROssendorfssendorf COCOolantolant MMixing Test Facilityixing Test FacilityC
oo
lan
t M
ixin
gC
oo
lan
t M
ixin
g
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Nuclear Safety Research
Wire Mesh Sensor (Pos. 1)
Pos. 1Pos. 1
Pos. 2Pos. 2
Pos. 4Pos. 4
Pos. 3Pos. 3
Dimensionless Mixing Scalar:Dimensionless Mixing Scalar:
ΘΘ x,y,zx,y,z (t) = (c (t) = (c x,y,zx,y,z -- ccrefref)/(c)/(cslugslug -- ccrefref))
cref – Reference Concentration Reactor (0)
cslug – Concentration Slug (1)
c x,y,z – Local Concentration
Conductivity Measurements with Wire Mesh SensorsConductivity Measurements with Wire Mesh SensorsC
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Nuclear Safety Research
� Mesh: 3.6 million nodes and 6.5
million hybrid elements
� Combination of Hexahedral and
Tetrahedral cells, mesh
refinement at the perforated
drum, in the lower support plate
and at the wall regions of the
cold legs
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Nuclear Safety ResearchBDT: Transport of the Slugs (i)BDT: Transport of the Slugs (i)C
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Institute of Safety Research � FWSS � Dr. Thomas Höhne � www.fzd.de � 19.03.2010 60
Nuclear Safety ResearchBDT: Transport of the Slugs (ii)BDT: Transport of the Slugs (ii)C
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Institute of Safety Research � FWSS � Dr. Thomas Höhne � www.fzd.de � 19.03.2010 61
Nuclear Safety Research
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Institute of Safety Research � FWSS � Dr. Thomas Höhne � www.fzd.de � 19.03.2010 62
Nuclear Safety Research
ConcludingConcluding
RemarksRemarks
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Institute of Safety Research � FWSS � Dr. Thomas Höhne � www.fzd.de � 19.03.2010 63
Nuclear Safety Research
��Computational fluid dynamics (CFD)Computational fluid dynamics (CFD) is one of the branches of is one of the branches of fluid mechanicsfluid mechanics that uses that uses numerical methodsnumerical methods and and algorithmsalgorithms to to solve and analyze problems that involve fluid flows. solve and analyze problems that involve fluid flows.
��Computers are used to perform the millions of calculations Computers are used to perform the millions of calculations required to simulate the interaction of liquids and gases with required to simulate the interaction of liquids and gases with surfaces defined by boundary conditions. surfaces defined by boundary conditions.
�� Even with highEven with high--speed speed supercomputerssupercomputers only approximate only approximate solutions can be achieved in many cases. solutions can be achieved in many cases.
��Ongoing research, however, may yield software that improves Ongoing research, however, may yield software that improves the accuracy and speed of complex simulation scenarios such as the accuracy and speed of complex simulation scenarios such as transonic or transonic or turbulentturbulent flows. flows.
�� Validation and verification of such software is necessary using Validation and verification of such software is necessary using high resolution experiments.high resolution experiments.
Concluding RemarksConcluding RemarksC
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Nuclear Safety Research
Thank You!Thank You!