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Norajitra, P.; Krauss, W.; Kruessmann, R.; Oberheide, V.; Giniyatulin, R.; Kuznetsov, V.; Mazul, I.; Ovchinnikov, I.; Ihli, Th.; Janeschitz, G.
Books of invited abstracts2006
Books of invited abstracts2006
AbstractAbstract
[en] In the course of the He-cooled divertor development [P. Norajitra et al., He-cooled divertor for DEMO: Experimental verification of the conceptual modular design, Fusion Engineering and Design 81 (2006) 341-346] at Forschungszentrum Karlsruhe, two modular concepts based on the use of multiple-jet cooling (HEMJ) and a slot flow promoter (HEMS), respectively, have been found to be promising. The modular design helps reduce thermal stresses. Goal is to reach a HHF of at least 10 MW/m2. Both concepts use small cooling finger modules which consist of a tungsten tile as thermal shield brazed to a pressure-carrying finger-like structure made of a tungsten alloy, such as W-1%La2O3. The cooling fingers are fixed to the supporting structure made of ODS steel via a transition piece with Cu filling and conical lock. The divertor is cooled with helium at 10 MPa and inlet/outlet temperatures of 600 o/700 oC. The accompanying issues relevant to the design are material and fabrication technologies, analyses, and experiments. The choice of tungsten as divertor material is based on its high resistance against sputtering. It is a low-activating and possesses a high melting point, high thermal conductivity, and relatively low thermal expansion. On the other hand, the temperature window range for the design is restricted by the recrystallisation and ductile-brittle transition temperatures of tungsten which are estimated to be about 1300 oC and 600 oC, respectively, under neutron irradiation. A series of technological breakthroughs are necessary for obtaining a functioning design. This has been demonstrated within the framework of cooperation with the Efremov Institute, St. Petersburg, Russia, in particular for the joining of W-W and/or W-steel components as well as the fabrication technology for W parts. Based on the knowledge gained by these test results, a series of W 1-finger mock-ups have been manufactured for the full tests in a helium loop (10 MPa, 600 oC) at Efremov using the TSEFEY EB facility for heat load simulation. The heat flux was varied stepwise between 3-12 MW/m2 with 10 temperature cycles during each step simulated by switching beam on and off. First two mock-ups were successfully tested. They withstood the specified heat load of 10 MW/m2. Only at elevated heat loads between 11-12 MW/m2 crack failure in the first mock-up and leakage failure in the second mock-up were detected. Post examinations for these mock-ups tested are underway. Further experiments are running. The test series will last until mid-2006 Discussion of these issues and state of the art of divertor development shall be the subjects of this paper. (author)
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Warsaw University of Technology, Warsaw (Poland). Funding organisation: AREVA, rue Le Peletier 27-29, Paris Cedex 09 (France); 515 p; 2006; p. 417; 24. Symposium on Fusion Technology - SOFT 2006; Warsaw (Poland); 11-15 Sep 2006; Also available from http://www.soft2006.materials.pl. Will be published also by Elsevier in ''Fusion and Engineering Design'' (full text papers)
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