Nuclear powered heat pumps for near-term process heat applications von Marmier, A., Fütterer, M.A.

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HTR-PM fuel pebble irradiation qualification in the high flux reactor in Petten von Knol, S., de Groot, S., Salama, R.V., Best, J., Bakker, K., Bobeldijk, I., Westlake, J.R., Fütterer, M.A., Laurie, M., Tang, Chunhe, Liu, Rongzheng, Liu, Bing, Zhao, Hongsheng

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Long term out-of-pile thermocouple tests in conditions representative for nuclear gas-cooled high temperature reactors von Laurie, M., Fourrez, S., Fütterer, M.A., Lapetite, J.M., Sadli, M., Morice, R., Failleau, G.

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Modelling of the HFR-EU1BIS experiment and thermomechanical evaluation von de Groot, S., Bakker, K., van Heek, A.I., Fütterer, M.A.

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The ARCHER project (Advanced High-Temperature Reactors for Cogeneration of Heat and Electricity R&D) von Knol, S., Fütterer, M.A., Roelofs, F., Kohtz, N., Laurie, M., Buckthorpe, D., Scheuermann, W.

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Tritium control modelling for a helium cooled lithium–lead blanket of a fusion power reactor von Farabolini, W., Ciampichetti, A., Dabbene, F., Fütterer, M.A., Giancarli, L., Laffont, G., Puma, A. Li, Raboin, S., Poitevin, Y., Ricapito, I., Sardain, P.

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New Temperature Monitoring Devices for High-Temperature Irradiation Experiments in the High Flux Reactor Petten von Laurie, M., Futterer, M. A., Lapetite, J. M., Fourrez, S., Morice, R.

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Calculations of the tritium re-emission rate in the DEMO first wall von Ogorodnikova, O.V., Fütterer, M.A., Serra, E., Benamati, G.

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Generation IV Reactor Safety and Materials Research by the Institute for Energy and Transport at the European Commission's Joint Research Centre von Tuček, K., Tsige-Tamirat, H., Ammirabile, L., Lázaro, A., Grah, A., Carlsson, J., Döderlein, Ch, Oettingen, M., Fütterer, M.A., D’Agata, E., Laurie, M., Turba, K., Ohms, C., Nilsson, K.-F., Hähner, P.

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JRC's on-line fission gas release monitoring system in the high flux reactor Petten von Laurie, M., Fütterer, M.A., Appelman, K.H., Lapetite, J.M., Marmier, A., Berg, G.

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Hydrogen isotope permeation through and inventory in the first wall of the water cooled Pb–17Li blanket for DEMO von Ogorodnikova, O.V., Fütterer, M.A., Serra, E., Benamati, G., Salavy, J.-F., Aiello, G.

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EUROPAIRS: The European project on coupling of High Temperature Reactors with industrial processes von Angulo, C., Bogusch, E., Bredimas, A., Delannay, N., Viala, C., Ruer, J., Muguerra, Ph, Sibaud, E., Chauvet, V., Hittner, D., Fütterer, M.A., de Groot, S., von Lensa, W., Verfondern, K., Moron, R., Baudrand, O., Griffay, G., Baaten, A., Segurado-Gimenez, J.

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Qualification of HTR pebbles by X-ray tomography and thermal analysis von Hania, P.R., Janssen, B., Fedorov, A.V., Knol, S., de Groot, S., Metten, L., van de Sande, A., Fütterer, M.A.

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Tritium permeation through helium-heated steam generators of ceramic breeder blankets for DEMO von Fütterer, Michael A., Raepsaet, Xavier, Proust, Eric

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Candidate blanket concepts for a European fusion power plant study von Giancarli, L, Ferrari, M, Fütterer, M.A, Malang, S

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Revisiting the concept of HTR wallpaper fuel von Marmier, A., Fütterer, M.A., Tuček, K., de Haas, Han, Kuijper, Jim C., Kloosterman, Jan Leen

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Status of the design and performances of the WCLL test blanket module for ITER-FEAT von Poitevin, Y, Fütterer, M.A, Giancarli, L, Li Puma, A, Salavy, J.-F, Szczepanski, J

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Potential and limits of water-cooled Pb–17Li blankets and divertors for a fusion power plant von Fütterer, M.A, Barleon, L, Giancarli, L, Puma, A.Li, Ogorodnikova, O.V, Poitevin, Y, Salavy, J.F, Szczepanski, J, Vella, G

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Qualification of HTR pebbles by X-ray tomography and thermal analysis: 5th International Topical Meeting on High Temperature Reactor Technology (HTR 2010) von HANIA, P. R, JANSSEN, B, FEDOROV, A. V, KNOL, S, DE GROOT, S, METTEN, L, DE SANDE, A. Van, FÜTTERER, M. A

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Performance of the TAURO blanket system associated with a liquid-metal cooled divertor von Golfier, H, Aiello, G, Fütterer, M.A, Gasse, A, Giancarli, L, Poitevin, Y, Salavy, J.F, Severi, Y, Szczepanski, J

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