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