TY - JOUR
T1 - Plasma–wall interaction studies within the EUROfusion consortium: progress on plasma-facing components development and qualification
JF - Nuclear Fusion
Y1 - 2017
A1 - Brezinsek, S.
A1 - Coenen, J. W.
A1 - Schwartz-Selinger, T.
A1 - Schmid, K.
A1 - Kirschner, A.
A1 - Hakola, A.
A1 - Tabares, F. L.
A1 - van der Meiden, H. J.
A1 - Mayoral, M.
A1 - Reinhart, M.
A1 - Tsitrone, E.
A1 - Vernimmen, J. W. M.
A1 - Morgan, T. W.
A1 - Ahlgren, T.
A1 - Aints, M.
A1 - Airila, M.
A1 - Almaviva, S.
A1 - Alves, E.
A1 - Angot, T.
A1 - Anita, V.
A1 - R. Arredondo Parra
A1 - Aumayr, F.
A1 - Balden, M.
A1 - Bauer, J.
A1 - Ben Yaala, M.
A1 - Berger, B. M.
A1 - Bisson, R.
A1 - Björkas, C.
A1 - Bogdanovic Radovic, I.
A1 - Borodin, D.
A1 - Bucalossi, J.
A1 - Butikova, J.
A1 - Butoi, B.
A1 - Cadez, I.
A1 - Caniello, R.
A1 - Caneve, L.
A1 - Cartry, G.
A1 - Catarino, N.
A1 - Čekada, M.
A1 - Ciraolo, G.
A1 - Ciupinski, L.
A1 - Colao, F.
A1 - Corre, Y.
A1 - Costin, C.
A1 - Craciunescu, T.
A1 - Cremona, A.
A1 - de Angeli, M.
A1 - de Castro, A.
A1 - Dejarnac, R.
A1 - Dellasega, D.
A1 - Dinca, P.
A1 - Dittmar, T.
A1 - Dobrea, C.
A1 - Hansen, P.
A1 - Drenik, A.
A1 - Eich, T.
A1 - Elgeti, S.
A1 - Falie, D.
A1 - Fedorczak, N.
A1 - Ferro, Y.
A1 - Fornal, T.
A1 - Fortuna, E.
A1 - Gao, L.
A1 - Gasior, P.
A1 - Gherendi, M.
A1 - Ghezzi, F.
A1 - Gosar, Z.
A1 - Greuner, H.
A1 - Grigore, E.
A1 - Grisolia, C.
A1 - Groth, M.
A1 - Gruca, M.
A1 - Grzonka, J.
A1 - Gunn, J. P.
A1 - Hassouni, K.
A1 - Heinola, K.
A1 - Höschen, T.
A1 - Huber, S.
A1 - Jacob, W.
A1 - Jepu, I.
A1 - Jiang, X.
A1 - Jogi, I.
A1 - Kaiser, A.
A1 - Karhunen, J.
A1 - Kelemen, M.
A1 - Köppen, M.
A1 - Koslowski, H. R.
A1 - Kreter, A.
A1 - Kubkowska, M.
A1 - Laan, M.
A1 - Laguardia, L.
A1 - Lahtinen, A.
A1 - Lasa, A.
A1 - Lazic, V.
A1 - Lemahieu, N.
A1 - Likonen, J.
A1 - Linke, J.
A1 - Litnovsky, A.
A1 - Linsmeier, C.
A1 - Loewenhoff, T.
A1 - Lungu, C.
A1 - Lungu, M.
A1 - Maddaluno, G.
A1 - Maier, H.
A1 - Makkonen, T.
A1 - Manhard, A.
A1 - Marandet, Y.
A1 - Markelj, S.
A1 - Marot, L.
A1 - Martin, C.
A1 - Martin-Rojo, A. B.
A1 - Martynova, Y.
A1 - Mateus, R.
A1 - Matveev, D.
A1 - Mayer, M.
A1 - Meisl, G.
A1 - Mellet, N.
A1 - Michau, A.
A1 - Miettunen, J.
A1 - Möller, S.
A1 - Mougenot, J.
A1 - Mozetic, M.
A1 - Nemanič, V.
A1 - Neu, R.
A1 - Nordlund, K.
A1 - Oberkofler, M.
A1 - Oyarzabal, E.
A1 - Panjan, M.
A1 - Pardanaud, C.
A1 - Paris, P.
A1 - Passoni, M.
A1 - Pegourie, B.
A1 - Pelicon, P.
A1 - Petersson, P.
A1 - Piip, K.
A1 - Pintsuk, G.
A1 - Pompilian, G. O.
A1 - Popa, G.
A1 - Porosnicu, C.
A1 - Primc, G.
A1 - Probst, M.
A1 - Räisänen, J.
A1 - Rasinski, M.
A1 - Ratynskaia, S.
A1 - Reiser, D.
A1 - Ricci, D.
A1 - Richou, M.
A1 - Riesch, J.
A1 - Riva, G.
A1 - Rosinski, M.
A1 - Roubin, P.
A1 - Rubel, M.
A1 - Ruset, C.
A1 - Safi, E.
A1 - Sergienko, G.
A1 - Siketic, Z.
A1 - Sima, A.
A1 - Spilker, B.
A1 - Stadlmayr, R.
A1 - Steudel, I.
A1 - Ström, P.
A1 - Tadic, T.
A1 - Tafalla, D.
A1 - Tale, I.
A1 - Terentyev, D.
A1 - Terra, A.
A1 - Tiron, V.
A1 - Tiseanu, I.
A1 - Tolias, P.
A1 - Tskhakaya, D.
A1 - Uccello, A.
A1 - Unterberg, B.
A1 - Uytdenhoven, I.
A1 - Vassallo, E.
A1 - Vavpetic, P.
A1 - Veis, P.
A1 - Velicu, I. L.
A1 - Voitkans, A.
A1 - von Toussaint, U.
A1 - Weckmann, A.
A1 - Wirtz, M.
A1 - Zaloznik, A.
A1 - Zaplotnik, R.
A1 - WP PFC contributors
AB - The provision of a particle and power exhaust solution which is compatible with first-wall components and edge-plasma conditions is a key area of present-day fusion research and mandatory for a successful operation of ITER and DEMO. The work package plasma-facing components (WP PFC) within the European fusion programme complements with laboratory experiments, i.e. in linear plasma devices, electron and ion beam loading facilities, the studies performed in toroidally confined magnetic devices, such as JET, ASDEX Upgrade, WEST etc. The connection of both groups is done via common physics and engineering studies, including the qualification and specification of plasma-facing components, and by modelling codes that simulate edge-plasma conditions and the plasma–material interaction as well as the study of fundamental processes. WP PFC addresses these critical points in order to ensure reliable and efficient use of conventional, solid PFCs in ITER (Be and W) and DEMO (W and steel) with respect to heat-load capabilities (transient and steady-state heat and particle loads), lifetime estimates (erosion, material mixing and surface morphology), and safety aspects (fuel retention, fuel removal, material migration and dust formation) particularly for quasi-steady-state conditions. Alternative scenarios and concepts (liquid Sn or Li as PFCs) for DEMO are developed and tested in the event that the conventional solution turns out to not be functional. Here, we present an overview of the activities with an emphasis on a few key results: (i) the observed synergistic effects in particle and heat loading of ITER-grade W with the available set of exposition devices on material properties such as roughness, ductility and microstructure; (ii) the progress in understanding of fuel retention, diffusion and outgassing in different W-based materials, including the impact of damage and impurities like N; and (iii), the preferential sputtering of Fe in EUROFER steel providing an in situ W surface and a potential first-wall solution for DEMO.
VL - 57
IS - 11
U1 - PSI
U2 - PMI
U5 - 4f90e0cf51291a6cb8b6e575c66f5043
ER -
TY - JOUR
T1 - Surface modifications and deuterium retention in polycrystalline and single crystal tungsten as a function of particle flux and temperature
JF - Journal of Nuclear Materials
Y1 - 2017
A1 - Buzi, L.
A1 - De Temmerman, G.
A1 - Matveev, D.
A1 - Reinhart, M.
A1 - Schwartz-Selinger, T.
A1 - Rasinski, M.
A1 - Unterberg, B.
A1 - Linsmeier, C.
A1 - Van Oost, G.
AB - The effects of particle flux and exposure temperature on surface modifications and deuterium (D) retention were systematically investigated on four different tungsten (W) microstructures. As-received, recrystallized, and single crystal W samples were exposed to D plasmas at surface temperatures of 530–1170 K. Two different ranges of D ion fluxes (1022 and 1024 D+m−2s−1) were used with the ion energy of 40 eV and particle fluence of 1026 D+m−2. Increasing the particle flux by two orders of magnitude caused blister formation and D retention even at temperatures above 700 K. The main effect of increasing the particle flux on total D retention was the shifting of temperature at which the retention was maximal towards higher temperatures. Diffusion-trapping simulations were used to fit the thermal desorption spectroscopy (TDS) release peaks of D, yielding one or two types of trapping sites with de-trapping energies around 2 eV.
VL - 495
U1 - PSI
U2 - PMI
U5 - 6dde5204bf1c0e9821bf878f41cb8f66
ER -