FZK - Fusion
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Design and testing of theITER ECRH Upper Launcher
ECHULA (ECH UpperLauncher) partners:
1 | 5th IAEA Tech. Meeting on ECRH – Gandhinagar 18-20 Feb 09
A. Vaccaro et al.
Fluid dynamics and thermal analysisFor the ITER ECH Upper Launcher
A. Vaccaroa, R. Heidingera, W. Leonhardtb, A. Meiera,D. Melleinb, T. Scherera, A.Serikovc, P. Späha, D. Straußa
Forschungszentrum Karlsruhe, Association FZK-Euratoma) Institute for Materials Research b) Institute for Pulsed Power and Microwave Technologyc) Institute for Reactor Safety
55thth IAEA Technical Meeting on ECRH IAEA Technical Meeting on ECRHGandhinagar – 18-20 February 2009Gandhinagar – 18-20 February 2009
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
The Upper Launcher in The Upper Launcher in ITERITER
BSM
Flangeconnection
Socket
Launcher Back-end
Main structure
Support Flange
Main Frame
Closure Plate
2 | 5th IAEA Tech. Meeting on ECRH – Gandhinagar 18-20 Feb 09
A. Vaccaro et al.
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
The Blanket Shield Module in the UPPThe Blanket Shield Module in the UPP
Front flange
Rear flange
Bolts are used to connectthe Blanket Shield Moduleto the mainframe of the UPP
3 | 5th IAEA Tech. Meeting on ECRH – Gandhinagar 18-20 Feb 09
A. Vaccaro et al.
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Modelling Modelling OverviewOverview
EM Analysis (FEM) CFD Analysis (MCNP+Finite diff.)
Mech. Loads
Thermal Loads
4 | 5th IAEA Tech. Meeting on ECRH – Gandhinagar 18-20 Feb 09
A. Vaccaro et al.
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Corner prototype and LHT facilityCorner prototype and LHT facility
The corner prototype is installed in the Launcher Handling Test facility at FZK.An active circuit provides feedwater at imposed temperature, pressure and mass flow rate.
Thermocouples
Graphite paint
5 | 5th IAEA Tech. Meeting on ECRH – Gandhinagar 18-20 Feb 09
A. Vaccaro et al.
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Shock cooling experimentShock cooling experiment
The same (ideal) event is simulated by CFD analysis. The comparison between the simulation and the experiment will provide information about the validity of the model.
The prototype is heated up to 95°C. When the equilibrium is reached, water at 25°C starts flowing into the cooling channel.The temperature is monitored by the thermocouples and IR imaging.
6 | 5th IAEA Tech. Meeting on ECRH – Gandhinagar 18-20 Feb 09
A. Vaccaro et al.
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
CFD Model – The „frozen“ approachCFD Model – The „frozen“ approach
- Constant properties are assumed.- Steady state analysis to asses the flow field and transport properties- Transient analysis performed solving only the energy equation.- Computation time reduced from 1.5 weeks to few hours
7 | 5th IAEA Tech. Meeting on ECRH – Gandhinagar 18-20 Feb 09
A. Vaccaro et al.
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Wall temperatures. ThermocouplesWall temperatures. Thermocouples
The curves show a good prediction of the heat exchange.
The delays between the curves are determined by the real trends of the inflow.
8 | 5th IAEA Tech. Meeting on ECRH – Gandhinagar 18-20 Feb 09
A. Vaccaro et al.
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Wall temperatures – IR imagingWall temperatures – IR imaging
9 | 5th IAEA Tech. Meeting on ECRH – Gandhinagar 18-20 Feb 09
A. Vaccaro et al.
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Heat loads on the corner of the BSMHeat loads on the corner of the BSM
Volumetric heat loads range from1.6 to 3 MW/m3
The model is divided into several sectorsto take into account of the non-constantheat deposition in the steel andIn the water (30-60%!)
10 | 5th IAEA Tech. Meeting on ECRH – Gandhinagar 18-20 Feb 09
A. Vaccaro et al.
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Nuclear heating – Steady state studyNuclear heating – Steady state study
twater = 11°CG = 4.5kg/sP = 138kW
High values on the flange
But
The steady-state scenario is not realistic.
The power production in ITER is pulsed.
11 | 5th IAEA Tech. Meeting on ECRH – Gandhinagar 18-20 Feb 09
A. Vaccaro et al.
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Nuclear heating – Transient study 1Nuclear heating – Transient study 1
The simulation is performed over 9 successive power cycles each one with 500 s power on followed by 1500 s power off.
12 | 5th IAEA Tech. Meeting on ECRH – Gandhinagar 18-20 Feb 09
A. Vaccaro et al.
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Nuclear heating – Transient study 2Nuclear heating – Transient study 2
13 | 4-5 Feb 2009
A. Vaccaro
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Nuclear heating – Transient study 2Nuclear heating – Transient study 2
t=0 t=250 t=500
t=1000 t=1500
14 | 5th IAEA Tech. Meeting on ECRH – Gandhinagar 18-20 Feb 09
A. Vaccaro et al.
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
Outlook: extension to the complete cooling circuitOutlook: extension to the complete cooling circuit
Front flange
Rear flange
First Wall Panel
By this simulation the temperaturedistribution in the whole connecting flanges of the BSM can be calculated.This result is needed for the design of the bolted connection.
15 | 5th IAEA Tech. Meeting on ECRH – Gandhinagar 18-20 Feb 09
A. Vaccaro et al.
KIT - Die Kooperation von
Forschungszentrum Karlsruhe GmbH
und Universität Karlsruhe (TH)
ConclusionConclusion
The Blanket Shield Module in the UPP is a challenging component due to the high thermal and mechanical loads to which it is subjected.
The shock-cooling experiments on the corner prototype and the CFD simulation presented in this paper are used as instrument to verify the efficacy of the cooling system.
The results also show that the cooling system is able to cool efficiently the walls and the flange of the BSM, when the nuclear heat production and the pulsed operation of the ITER reactor are taken into account.
Modelling is a necessary tool for the design of some key features of the UPP, like the bolted connection of the BSM and the fixation of the entire structure to the Upper Port.
16 | 5th IAEA Tech. Meeting on ECRH – Gandhinagar 18-20 Feb 09
A. Vaccaro et al.
Top Related