This title appears in the Scientific Report :
2016
Advanced materials development for DEMO divertor and first wall components
Advanced materials development for DEMO divertor and first wall components
Advanced materials development for DEMO divertor and first wall componentsCh. Linsmeier1, J.W. Coenen1, J. Riesch2, B. Unterberg1, Ph. Mertens1, J. Brinkmann1, J. Engels1, H. Gietl2, A. Houben1, B. Jasper1, F. Klein1, M. Li2, A. Litnovsky1, Y. Mao1, T. Wegener1, J.-H. You21Forschungszentrum Jülich G...
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Personal Name(s): | Linsmeier, Ch. (Corresponding author) |
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Coenen, J. W. / Riesch, J. / Unterberg, B. / Mertens, Ph. / Brinkmann, J. / Engels, J. / Gietl, H. / Houben, A. / Jasper, B. / Klein, F. / Li, M. / Litnovsky, A. / Mao, Y. / Wegener, T. / You, J.-H. | |
Contributing Institute: |
Plasmaphysik; IEK-4 |
Imprint: |
2016
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Conference: | The 1st International 'All -about -Divertor' Symposium, Kyoto (Japan), 2016-10-14 - 2016-10-15 |
Document Type: |
Abstract |
Research Program: |
Helmholtz Interdisciplinary Doctoral Training in Energy and Climate Research (HITEC) Methods and Concepts for Material Development |
Publikationsportal JuSER |
Advanced materials development for DEMO divertor and first wall componentsCh. Linsmeier1, J.W. Coenen1, J. Riesch2, B. Unterberg1, Ph. Mertens1, J. Brinkmann1, J. Engels1, H. Gietl2, A. Houben1, B. Jasper1, F. Klein1, M. Li2, A. Litnovsky1, Y. Mao1, T. Wegener1, J.-H. You21Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung – Plasmaphysik, Partner of the Trilateral Euregio Cluster (TEC), 52425 Jülich, Germany 2Max-Planck-Institut für Plasmaphysik, Boltzmannstr. 2, 85748 Garching b. München, GermanyThe plasma-facing components for ITER, divertor and first wall, are well developed and mature to withstand the expected particle and power loads, as well as the neutron damage envisaged over the ITER lifetime. Extrapolating towards the operating conditions for a DEMO fusion reactor, however, extends their thermo-mechanical safety margins due to higher temperatures and large neutron doses. Tungsten is also the favorable element for the plasma-facing elements in a DEMO reactor due to its high sputtering threshold and hence low erosion rates. Hence, plasma-facing and heat sink materials need to be adapted in order to operate within the necessary temperature window with sufficient thermo-mechanical stability.Composites which are tailored for the specific operation conditions are proposed concepts to close the material gap. Tungsten for high heat flux components is replaced by tungsten-based composites which exhibit strongly enhanced toughness values due to extrinsic toughening mechanisms, provided by fiber reinforcement. The current research status and fabrication routes for such composites are outlined in this presentation.In a fusion power plant with a high duty cycle, transmutation to radioactive isotopes occurs during operation. The release of these isotopes must be avoided in an accidental scenario, e.g. a loss-of-coolant event with air ingress. A solution to provide intrinsic safety for such scenarios are tungsten-based alloys which reduce the oxidation and subsequent release by oxide sublimation at elevated temperatures. Current candidate alloys and their self-passivating behavior are presented in this contribution. Further aspects like tritium permeation barriers to minimize fuel losses will also be discussed.This overview talk demonstrates materials solutions for a DEMO power reactor, required to apply the currently well-established ITER divertor and first wall concepts |