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000188873 1001_ $$0P:(DE-Juel1)156199$$aBlommaert, M.$$b0$$eCorresponding Author$$ufzj
000188873 245__ $$aAn automated approach to magnetic divertor configuration design
000188873 260__ $$aVienna$$bIAEA$$c2015
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000188873 520__ $$aAutomated methods based on optimization can greatly assist computational engineering design in many areas. In this paper an optimization approach to the magnetic design of a nuclear fusion reactor divertor is proposed and applied to a tokamak edge magnetic configuration in a first feasibility study. The approach is based on reduced models for magnetic field and plasma edge, which are integrated with a grid generator into one sensitivity code. The design objective chosen here for demonstrative purposes is to spread the divertor target heat load as much as possible over the entire target area. Constraints on the separatrix position are introduced to eliminate physically irrelevant magnetic field configurations during the optimization cycle. A gradient projection method is used to ensure stable cost function evaluations during optimization. The concept is applied to a configuration with typical Joint European Torus (JET) parameters and it automatically provides plausible configurations with reduced heat load.
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000188873 7001_ $$0P:(DE-Juel1)162424$$aDekeyser, W.$$b1
000188873 7001_ $$0P:(DE-HGF)0$$aBaelmans, M.$$b2
000188873 7001_ $$0P:(DE-HGF)0$$aGauger, N. R.$$b3
000188873 7001_ $$0P:(DE-Juel1)5006$$aReiter, D.$$b4$$ufzj
000188873 773__ $$0PERI:(DE-600)2037980-8$$a10.1088/0029-5515/55/1/013001$$gVol. 55, no. 1, p. 013001 -$$n1$$p013001 -$$tNuclear fusion$$v55$$x1741-4326$$y2015
000188873 8564_ $$uhttp://iopscience.iop.org/0029-5515/55/1/013001
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