Best Practice Guidelines for the Use of CFD in Nuclear Reactor Safety Applications _ CSNI
Application of CFD for nuclear reactor safety analyses of CFD for nuclear reactor safety analyses...
Transcript of Application of CFD for nuclear reactor safety analyses of CFD for nuclear reactor safety analyses...
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 1
Application of CFD for nuclear reactor safety analyses
Bogdán Yamajiassistant researcher
Institute of Nuclear TechniquesBudapest University of Technology and Economics
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 2
Wide spectrum of CFD research• CFD projects – GenII+III and training reactor:
– Coolant mixing in the fuel assembly : in the rod bundle and assembly head – VVER-440
– Subchannel calculations for VVER-440 fuel assembly– Coolant mixing in RPV - VVER-440 – Coolant mixing in RPV - VVER-1000– Mixing processes in the cooling pond– Thermal-hydraulic processes in the Training Reactor– Coolant mixing in the fuel assembly – EK-10
(BME Training Reactor)– One-phase CFD analyses of the serious incident occurred
in Paks-2, 2003: course of the incident, post-incident state of the system, calculations backing the recovery work
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 3
Wide spectrum of CFD research• CFD projects – GenIV and fusion:
– CFD validation with measurements of supercritical water – Mixing and thermal-hydraulics in HPLWR fuel assembly– CFD modelling of annular flow of lead-bismuth eutectic along
heated rod – measurement data from FZK test facility– CFD analyses of molten salt reactors– ITER related CFD research
• HCPB Test Blanket Module analyses: TBM stiffening grids, manifold, breeding unit, cap, first wall
• HETRA experimental facility design and analysis• GRICAMAN experimental facility design
• Codes: ANSYS CFX (v.11, 12), ICEM CFD, Workbench– (OpenFOAM - open source)
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 4
• 18 898 758 elements
VVER-440/213 detailed model
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 5* Flomix_D11_WP4_Finalreport
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VVER-440/213 – mixing factors at the core inlet
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 6
VVER-1000 mixing in RPVOECD/NEA benchmark: coolant mixing in RPV and temperature distribution at the core inletmeasurement data: Kozloduy NPP
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 7
KKTKT
TTTT
delta
idataicalc
idataicalci
13][][ ,,
minmax
,,
measurement
difference
VVER-1000 mixing in RPV
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 8
• EK10 - BME Training Reactor fuel assembly
• Coupled kinetics – analysis of power transients
Model length (Z direction) 540 mm
Fuel length 500 mm
Width in X and Y direction 32,5 mm
Fuel cladding outer diameter 10 mm
Fuel cladding inner diameter 7 mm
Training reactor fuel TH – EK-10
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 9
Assembly head
Fuel bundleSub-channel
VVER-440 fuel assembly
• Analysis of mixing in the head and the bundle• Verification of sub-channel codes• Analysis of new fuel assembly types• Validated against measurements of Kurchatov
Insititute
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 10
• Detailed analysis: mesh, turbulence modelling• Measurement data: Trupp and Azard,1975
M1 M2 M3
M4 M5 M6
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0.0 0.2 0.4 0.6 0.8 1.0y*
ExperimentM1M2M3M4M5M6
v2+
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ExperimentBSL Reynolds StressSSG Reynolds StressSSTk-epsilon
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VVER-440 fuel assembly – sub-channel calculations
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 11
• Convective mixing between sub-channels• Detailed analysis of spacing grids
VVER-440 fuel assembly – bundle calculations
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 12
S2:
(Tin >Tpc ; Tin =408°C)
• 3D CFX models, different turbulence modelling• measurement data by Swenson, Herkenrath,
Yamagata• Model development for supercritical water
behaviour
S1:
(Tin <Tpc ; Tin =390,85°C)
Supercritical waterCFX validation against three measurements
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 13
Flow direction
HPLWR (High Performance Light Water Reactor) fuel bundle
Supercritical water - HPLWR
• Steady state CFX calculations of ¼ HPLWR fuel bundle model• helical spacers• (Co-operation with IKE, University of Stuttgart)
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 1404. 06. 2009.
• Annular flow of lead-bismuth eutectic along a heated rod• Validation of CFD models and measurements of heated
Rod case by Forschungszentrum Karlsruhe (FZK)
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Annular Flow of LBE along a Heated Rod
• Different computational meshes• Analysis of turbulence modelling
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 16
MOSTCFD analyses of molten salt reactors
MOSARTMSRE
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 17
ITER
Helium Cooled Pebble Bed Test Blanket Module
ITER
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 18
Stiffening grid TBM Manifold
Caps Breeding unit
ITER
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 19
Application of PIV/LIF• Small-scale experimental facility for validation of
CFD calculations • Coolant mixing and thermal stratification• System components:
– PIV – Particle Image Velocimetry LIF – Laser Induced Fuorescece
• Seeding particles for PIV, fluorescent dye for LIF• 135 mJ, 532 nm Nd-YAG dual laser (15 Hz)• 2x(1600*1200) pixel digital camera (30 fps)• Software (Dynamic Studio)
– thermocouples, flow meters, etc– small plexiglas rectangular vessel („aquarium”)– engineering equipments (heaters, valves, pumps)
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 23
• Measurement of concentration/temperature
C=1
C=0
Application of PIV/LIF