4 research outputs found

    Power handling and vapor shielding of pre-filled lithium divertor targets

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    This dataset is the replication package on experimentation and modeling, accompanying the paper: Power handling and vapor shielding of pre-filled lithium divertor targets Magnum-PS

    Dataset underlying the paper: Using 3D-printed tungsten to optimize liquid metal divertor targets for flow and thermal stresses

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    Dataset accompanying the paper titled: Using 3D-printed tungsten to optimize liquid metal divertor targets for flow and thermal stresses. Includes experimental replication package and detailed information on conducted FEM modelin

    Damage evaluation of vertical targets and first walls during ITER-FEAT off-normal events

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    For modelling of hot plasma wall interaction, for calculation of erosion by evaporation of the ITER-FEAT vertical divertor target and for calculation of the impurity transport in the divertor, the 2-D R-MHD code FOREV-2 was developed. FOREV-2 uses a 21/2-D MHD model, a 2-D scheme for anisotropic radiation transport and a solution of the magnetic field equations in the plasma shield for all three components of the magnetic field. Disruption simulation experiments performed at the plasma gun facilities at TRINITI Troitsk were used for validation of FOREV-2 and for investigations of the MHD of typical plasma shields. The 2-D numerical analysis of the disruption simulation experiments allows to conclude that such experiments adequately simulate the Tokamak plasma shield properties and its dynamics. From the results of the numerical analysis of the simulation experiments it is concluded that turbulence in the Tokamak shields is absent and that the stability of the cold and dense part of the Tokamak plasma shields which determines the target erosion can be adequately modeled by FOREV-2 by use of the classical magnetic field diffusion coefficient. Line radiation and an appropriate model for anisotropic radiation transport are necessary for a realistic calculation of radiation from the plasma shield. Moreover inclusion of line radiation allows to get a realistic radiation cooling of the plasma shield after switching off the heating. (orig.)Available from TIB Hannover: ZA 5141(6582) / FIZ - Fachinformationszzentrum Karlsruhe / TIB - Technische InformationsbibliothekSIGLEDEGerman

    Experimental Project Results from the Design Institute for Physical Properties (DIPPR) of the American Institute of Chemical Engineers. 5

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