Title :
The ITER EC-H&CD Upper Launcher: FEM analyses of the blanket shield module with respect to surface and nuclear heat loads
Author :
Vaccaro, Alfredo ; Aiello, Giovanni ; Grossetti, G. ; Meier, A. ; Scherer, Theo ; Schreck, S. ; Spah, P. ; Straus, D. ; Serikov, A. ; Weinhorst, B.
Author_Institution :
Inst. for Appl. Mater. (IAM-AWP), Assoc. KIT-EURATOM, Karlsruhe, Germany
Abstract :
In the frame of the new grant signed in November 2011 between Fusion for Energy (F4E) and the ECHUL-CA consortium, the development process of the Electron Cyclotron Heating and Current Drive (EC H&CD) Upper Launcher (UL) in ITER has moved a step towards the final design phase. The Blanket Shield Module (BSM) is a plasma facing component located at the tip of the launcher. The structure consists of a first wall panel (FWP) and a shell both with embedded cooling channels. A flange on the rear part allows the BSM to be connected by bolts to the main frame of the UL. Being a plasma facing component, the BSM is subjected to severe heat loads due to both thermal and nuclear irradiation. The current baseline value of surface heat load during normal plasma operation is 0.5 MW/m2, while the volumetric nuclear heating is responsible for a total generation of about 160 kW. The temperature gradients resulting from the abovementioned heat loads have been assessed by FEM analyses. The temperature distributions are then transferred to a structural model for calculation of the induced thermal stresses. The surface heat load is applied to the FWP as a constant flux. The nuclear loads, instead, were assessed by MCNP calculations and are provided by means of a mesh tally with a grid step of 1 cm. The results have shown that the temperature reaches 260 °C at the FWP and at the flange of the BSM. As a consequence of large temperature gradients, high stresses (in the order of 200 MPa) are also induced at the inner cooling channels of the BSM´s structure.
Keywords :
Tokamak devices; fusion reactor blankets; fusion reactor design; fusion reactor materials; plasma radiofrequency heating; plasma temperature; plasma toroidal confinement; BSM; EC H and CD UL; EC H and CD development process; ECHUL-CA consortium; F4E; FEM analyses; FWP; ITER EC-H and CD upper launcher; MCNP calculations; blanket shield module; constant flux; current baseline value; electron cyclotron heating and current drive; embedded cooling channels; final design phase; first wall panel; fusion for energy; grant signed frame; grid step; induced thermal stress calculation; main frame UL; mesh tally; normal plasma operation; nuclear heat load; nuclear irradiation; nuclear loads; plasma facing component; severe heat loads; structural model; surface heat load; temperature distributions; temperature gradients; thermal irradiation; volumetric nuclear heating; Cooling; Flanges; Heating; Plasma temperature; Stress; Thermal analysis; FEM analysis; ITER; blanket shield module; sub-modeling; upper launcher;
Conference_Titel :
Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on
Conference_Location :
San Francisco, CA
Print_ISBN :
978-1-4799-0169-2
DOI :
10.1109/SOFE.2013.6635394