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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
* * *
* * *
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
0.0
0.2
0.4
0.6
0.8
1.0
1.2
1.4
0.0 0.2 0.4 0.6 0.8 1.0y*
ExperimentM1M2M3M4M5M6
v2+
0.0
0.2
0.4
0.6
0.8
1.0
1.2
1.4
1.6
0.0 0.2 0.4 0.6 0.8 1.0y*
ExperimentBSL Reynolds StressSSG Reynolds StressSSTk-epsilon
v2+
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)
14
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 1504. 06. 2009. 15
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 20
Application of PIV/LIF
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 21
Application of PIV/LIF
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 22
Application of PIV/LIF
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 23
• Measurement of concentration/temperature
C=1
C=0
Application of PIV/LIF
11-12 June 2009 2nd Consultancy Meeting of INPRO COOL Project 24
Application of PIV/LIF
Core and irradiating facilities•BME Training Reactor – 100 kW, pool type
•Irradiation channels, irradiation tunnel, pneumatic rabbit system
