Overview of manufacturing technologies under development in Russia for ITER plasma facing components von Giniyatulin, R.N., Mazul, I.V., Gervash, A.A., Guryeva, T.М., Kuznetcov, V.E., Makhankov, A.N., Okunev, A.A., Sevrukov, O.N.

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Electromagnetic Analysis of Options of the TRT Tokamak First Wall Panel Design and Its Optimization Based on Calculations for the Downward VDE Scenario von Piskarev, P. Yu, Mazul, I. V., Gapionok, E. I., Belov, A. V., Makhankov, A. N., Okuneva, E. V., Kolesnik, M. S., Kedrov, I. V., Gervash, A. A., Kavin, A. A., Lukash, V. E., Khayrutdinov, R. R.

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The development of technology of Be/CuCrZr joining using induction brazing von Gervash, A., Giniyatulin, R., Guryeva, T., Glazunov, D., Kuznetsov, V., Mazul, I., Ogursky, Piskarev, P., Safronov, V., Eaton, R., Raffray, R., Sevryukov, O.

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Analysis of Enhanced Heat Flux First Wall behavior under ITER Pulsed Loads von Sviridenko, M., Leshukov, A., Tomilov, S., Strebkov, Yu, Khokhlov, M., Okuneva, E., Gervash, A., Safronov, V., Raffray, R., Eaton, R., Gicquel, S., Calcagno, B.

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Erosion of beryllium under ITER – Relevant transient plasma loads von Kupriyanov, I.B., Nikolaev, G.N., Kurbatova, L.A., Porezanov, N.P., Podkovyrov, V.L., Muzichenko, A.D., Zhitlukhin, A.M., Gervash, A.A., Safronov, V.M.

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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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Study of the Bimetallic Joint CuCrZr/316L(N) von Kudryavceva, A.M., Ermakov, Boris S., Piskarev, P.Y., Gervash, Alexander A., Vologzhanina, S.A.

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EHF FW panel for ITER BM with mechanical attachment of the plasma-facing components von Tomilov, S., Sviridenko, M., Leshukov, A., Gervash, A., Okuneva, E., Mazul, I., Safronov, V., Calcagno, B., Eaton, R., Gicquel, S., Raffray, R.

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Development of a helium-cooled divertor concept: design-related requirements on materials and fabrication technology von Norajitra, P, Boccaccini, L.V, Diegele, E, Filatov, V, Gervash, A, Giniyatulin, R, Gordeev, S, Heinzel, V, Janeschitz, G, Konys, J, Krauss, W, Kruessmann, R, Malang, S, Mazul, I, Moeslang, A, Petersen, C, Reimann, G, Rieth, M, Rizzi, G, Rumyantsev, M, Ruprecht, R, Slobodtchouk, V

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Analysis results of the enhanced heat flux first wall panel elements von Tomilov, S., Sviridenko, M., Leshukov, A., Strebkov, Yu, Gervash, A., Mazul, I., Okuneva, E., Khokhlov, M., Safronov, V., Calcagno, B., Eaton, R., Raffray, R.

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Status of the beryllium tile bonding qualification activities for the manufacturing of the ITER first wall von Mitteau, Raphaël, Eaton, R., Perez, G., Zacchia, F., Banetta, S., Bellin, B., Gervash, A., Glazunov, D., Chen, J.

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Brazing of Be with CuCrZr-bronze using copper-based filler metal STEMET von Kalin, B.A., Suchkov, A.N., Fedotov, V.T., Sevryukov, O.N., Ivannikov, A.A., Gervash, A.A.

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Allowable heat load on the edge of the ITER first wall panel beryllium flat tiles von Mitteau, R., Eaton, R., Gervash, A., Kuznetcov, V., Davydov, V., Rulev, R.

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Progress on performance assessment of ITER enhanced heat flux first wall technology after neutron irradiation von Hirai, T, Bao, L, Barabash, V, Chappuis, Ph, Eaton, R, Escourbiac, F, Giqcuel, S, Merola, M, Mitteau, R, Raffray, R, Linke, J, Loewenhoff, Th, Pintsuk, G, Wirtz, M, Boomstra, D, Magielsen, A, Chen, J, Wang, P, Gervash, A, Safronov, V

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High heat flux testing of first wall mock-ups with and without neutron irradiation von Pintsuk, G., Bellin, B., Gervash, A., Linke, J., Litunovsky, N., Lorenzetto, P.

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Status of RF beryllium characterization for ITER Fist Wall von Kupriyanov, I.B., Nikolaev, G.N., Roedig, M., Gervash, A.А., Linke, I.J., Kurbatova, L.A., Perevalov, S.I., Giniyatulin, R.N.

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Analyses results of the EHF FW Panel with welded fingers von Sviridenko, M.N., Leshukov, A.Yu, Razmerov, A.V., Tomilov, S.N., Danilov, I.V., Strebkov, Yu.S., Mazul, I.V., Labusov, A., Gervash, A.A., Belov, A.V., Semichev, D.

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Russian development of enhanced heat flux technologies for ITER first wall von Mazul, I., Alekseev, A., Belyakov, V., Bondarchuk, D., Eaton, R., Escourbiac, F., Gervash, A., Glazunov, D., Kuznetsov, V., Merola, M., Labusov, A., Ovchinnikov, I., Raffray, R., Rulev, R.

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Preparation to manufacturing of ITER plasma facing components in Russia von Mazul, I.V., Belyakov, V.A., Giniatulin, R.N., Gervash, A.A., Kuznetsov, V.E., Makhankov, A.N., Sizenev, V.S.

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Helium-cooled divertor for DEMO: Manufacture and high heat flux tests of tungsten-based mock-ups von Norajitra, P., Gervash, A., Giniyatulin, R., Hirai, T., Janeschitz, G., Krauss, W., Kuznetsov, V., Makhankov, A., Mazul, I., Ovchinnikov, I., Reiser, J., Widak, V.

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