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FZK - Fusion KIT - Die Kooperation von Forschungszentrum Karlsruhe GmbH und Universität Karlsruhe (TH) Design and testing of the ITER ECRH Upper Launcher.

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Präsentation zum Thema: "FZK - Fusion KIT - Die Kooperation von Forschungszentrum Karlsruhe GmbH und Universität Karlsruhe (TH) Design and testing of the ITER ECRH Upper Launcher."—  Präsentation transkript:

1 FZK - Fusion KIT - Die Kooperation von Forschungszentrum Karlsruhe GmbH und Universität Karlsruhe (TH) Design and testing of the ITER ECRH Upper Launcher ECHULA (ECH UpperLauncher) partners: 1 | 5 th IAEA Tech. Meeting on ECRH – Gandhinagar Feb 09 A. Vaccaro et al. Fluid dynamics and thermal analysis For the ITER ECH Upper Launcher A. Vaccaro a, R. Heidinger a, W. Leonhardt b, A. Meier a, D. Mellein b, T. Scherer a, A.Serikov c, P. Späh a, D. Strauß a Forschungszentrum Karlsruhe, Association FZK-Euratom a) Institute for Materials Research b) Institute for Pulsed Power and Microwave Technology c) Institute for Reactor Safety 5 th IAEA Technical Meeting on ECRH Gandhinagar – February 2009

2 KIT - Die Kooperation von Forschungszentrum Karlsruhe GmbH und Universität Karlsruhe (TH) The Upper Launcher in ITER BSM Flange connection Socket Launcher Back-end Main structure Support Flange Main Frame Closure Plate 2 | 5 th IAEA Tech. Meeting on ECRH – Gandhinagar Feb 09 A. Vaccaro et al.

3 KIT - Die Kooperation von Forschungszentrum Karlsruhe GmbH und Universität Karlsruhe (TH) The Blanket Shield Module in the UPP Front flange Rear flange Bolts are used to connect the Blanket Shield Module to the mainframe of the UPP 3 | 5 th IAEA Tech. Meeting on ECRH – Gandhinagar Feb 09 A. Vaccaro et al.

4 KIT - Die Kooperation von Forschungszentrum Karlsruhe GmbH und Universität Karlsruhe (TH) Modelling Overview EM Analysis (FEM) CFD Analysis (MCNP+Finite diff.) Mech. Loads Thermal Loads 4 | 5 th IAEA Tech. Meeting on ECRH – Gandhinagar Feb 09 A. Vaccaro et al.

5 KIT - Die Kooperation von Forschungszentrum Karlsruhe GmbH und Universität Karlsruhe (TH) Corner 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 | 5 th IAEA Tech. Meeting on ECRH – Gandhinagar Feb 09 A. Vaccaro et al.

6 KIT - Die Kooperation von Forschungszentrum Karlsruhe GmbH und Universität Karlsruhe (TH) Shock 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 | 5 th IAEA Tech. Meeting on ECRH – Gandhinagar Feb 09 A. Vaccaro et al.

7 KIT - Die Kooperation von Forschungszentrum Karlsruhe GmbH und Universität Karlsruhe (TH) CFD 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 | 5 th IAEA Tech. Meeting on ECRH – Gandhinagar Feb 09 A. Vaccaro et al.

8 KIT - Die Kooperation von Forschungszentrum Karlsruhe GmbH und Universität Karlsruhe (TH) Wall 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 | 5 th IAEA Tech. Meeting on ECRH – Gandhinagar Feb 09 A. Vaccaro et al.

9 KIT - Die Kooperation von Forschungszentrum Karlsruhe GmbH und Universität Karlsruhe (TH) Wall temperatures – IR imaging 9 | 5 th IAEA Tech. Meeting on ECRH – Gandhinagar Feb 09 A. Vaccaro et al.

10 KIT - Die Kooperation von Forschungszentrum Karlsruhe GmbH und Universität Karlsruhe (TH) Heat loads on the corner of the BSM Volumetric heat loads range from 1.6 to 3 MW/m 3 The model is divided into several sectors to take into account of the non-constant heat deposition in the steel and In the water (30-60%!) 10 | 5 th IAEA Tech. Meeting on ECRH – Gandhinagar Feb 09 A. Vaccaro et al.

11 KIT - Die Kooperation von Forschungszentrum Karlsruhe GmbH und Universität Karlsruhe (TH) Nuclear heating – Steady state study t water = 11°C G = 4.5kg/s P = 138kW High values on the flange But The steady-state scenario is not realistic. The power production in ITER is pulsed. 11 | 5 th IAEA Tech. Meeting on ECRH – Gandhinagar Feb 09 A. Vaccaro et al.

12 KIT - Die Kooperation von Forschungszentrum Karlsruhe GmbH und Universität Karlsruhe (TH) Nuclear 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 | 5 th IAEA Tech. Meeting on ECRH – Gandhinagar Feb 09 A. Vaccaro et al.

13 KIT - Die Kooperation von Forschungszentrum Karlsruhe GmbH und Universität Karlsruhe (TH) Nuclear heating – Transient study 2 13 | 4-5 Feb 2009 A. Vaccaro

14 KIT - Die Kooperation von Forschungszentrum Karlsruhe GmbH und Universität Karlsruhe (TH) Nuclear heating – Transient study 2 t=0t=250t=500 t=1000t= | 5 th IAEA Tech. Meeting on ECRH – Gandhinagar Feb 09 A. Vaccaro et al.

15 KIT - Die Kooperation von Forschungszentrum Karlsruhe GmbH und Universität Karlsruhe (TH) Outlook: extension to the complete cooling circuit Front flange Rear flange First Wall Panel By this simulation the temperature distribution in the whole connecting flanges of the BSM can be calculated. This result is needed for the design of the bolted connection. 15 | 5 th IAEA Tech. Meeting on ECRH – Gandhinagar Feb 09 A. Vaccaro et al.

16 KIT - Die Kooperation von Forschungszentrum Karlsruhe GmbH und Universität Karlsruhe (TH) Conclusion 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 | 5 th IAEA Tech. Meeting on ECRH – Gandhinagar Feb 09 A. Vaccaro et al.


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