Development of a helium-cooled divertor: Material choice and technological studies von Norajitra, P., Boccaccini, L.V., Gervash, A., Giniyatulin, R., Holstein, N., Ihli, T., Janeschitz, G., Krauss, W., Kruessmann, R., Kuznetsov, V., Makhankov, A., Mazul, I., Moeslang, A., Ovchinnikov, I., Rieth, M., Zeep, B.

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Review of blanket designs for advanced fusion reactors von Ihli, T., Basu, T.K., Giancarli, L.M., Konishi, S., Malang, S., Najmabadi, F., Nishio, S., Raffray, A.R., Rao, C.V.S., Sagara, A., Wu, Y.

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Efficient helium cooling methods for nuclear fusion devices: Status and prospects von Ihli, T., Ilić, M.

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He-cooled divertor development for DEMO von Norajitra, P., Giniyatulin, R., Ihli, T., Janeschitz, G., Krauss, W., Kruessmann, R., Kuznetsov, V., Mazul, I., Widak, V., Ovchinnikov, I., Ruprecht, R., Zeep, B.

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Design update, thermal and fluid dynamic analyses of the EU-HCPB TBM in vertical arrangement von Cismondi, F., Kecskés, S., Ilic, M., Légrádi, G., Kiss, B., Bitz, O., Dolensky, B., Neuberger, H., Boccaccini, L.V., Ihli, T.

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HELOKA facility: Thermo-hydrodynamic model and control von Ghidersa, B.E., Marchese, V., Ionescu-Bujor, M., Ihli, T.H.

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He-cooled divertor for DEMO: Experimental verification of the conceptual modular design von Norajitra, P., Gervash, A., Giniyatulin, R., Ihli, T., Krauss, W., Kruessmann, R., Kuznetsov, V., Makhankov, A., Mazul, I., Ovchinnikov, I.

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DEMO maintenance scenarios: Scheme for time estimations and preliminary estimates for blankets arranged in multi-module segments von Nagy, D., Ihli, T., Filsinger, D., Gottfried, R.

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Thermohydraulic experimental design for the European Helium-Cooled-Pebble-Bed Test Blanket Module von Ilić, M., Kiss, B., Ihli, T.

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Design and performance study of the helium-cooled T-tube divertor concept von Ihli, T., Raffray, A.R., Abdel-Khalik, S.I., Shin, S.

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Fabrication of a He-cooled divertor module for DEMO reactor von Gervash, A., Giniyatulin, R., Ihli, T., Krauss, W., Makhankov, A., Mazul, I., Norajitra, P., Yablokov, N.

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Manufacturing aspects in the design of the breeder unit for helium cooled pebble bed blankets von Rey, J., Filsinger, D., Ihli, T., Polixa, C.

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An advanced He-cooled divertor concept: Design, cooling technology, and thermohydraulic analyses with CFD von Ihli, T., Kruessmann, R., Ovchinnikov, I., Norajitra, P., Kuznetsov, V., Giniyatulin, R.

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European development of He-cooled divertors for fusion power plants von Norajitra, P, Giniyatulin, R, Ihli, T, Janeschitz, G, Karditsas, P, Krauss, W, Kruessmann, R, Kuznetsov, V, Maisonnier, D, Mazul, I, Nardi, C, Ovchinnikov, I, Papastergiou, S, Pizzuto, A, Sardain, P

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HELOKA data acquisition and control system: Current development status von Jianu, A., Marchese, V., Ghidersa, B.E., Messemer, G., Ihli, T.

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Design optimization and experimental testing of the High-Flux Test Module of IFMIF von Leichtle, D., Arbeiter, F., Dolensky, B., Fischer, U., Gordeev, S., Heinzel, V., Ihli, T., Moeslang, A., Simakov, S.P., Slobodchuk, V., Stratmanns, E.

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Integration of an advanced He-cooled divertor in a DEMO-relevant tokamak geometry von Ihli, T., Hermsmeyer, S., Köhly, C., Norajitra, P.

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IFMIF High Flux Test Module—Recent progress in design and manufacturing von Leichtle, D., Arbeiter, F., Dolensky, B., Fischer, U., Gordeev, S., Heinzel, V., Ihli, T., Lang, K.-H., Moeslang, A., Simakov, S.P., Slobodchuk, V., Stratmanns, E.

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Numerical and Experimental Study of Unsteady Flow Field and Vibration in Radial Inflow Turbines von Kreuz-Ihli, T, Filsinger, D, Schulz, A, Wittig, S

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Recent progress in DEMO fusion core engineering: Improved segmentation, maintenance and blanket concepts von Ihli, T., Boccaccini, L.V., Janeschitz, G., Koehly, C., Maisonnier, D., Nagy, D., Polixa, C., Rey, J., Sardain, P.

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