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

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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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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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A water cooled lithium–lead blanket without tritium permeation barriers: feasibility and economical analysis von Kveton, O, Ricapito, I, Futterer, M.A, Benamati, G

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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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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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Economic viability of small nuclear reactors in future European cogeneration markets von Carlsson, Johan, Shropshire, David E., van Heek, Aliki, Fütterer, Michael A.

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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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Water-cooled Pb–17Li test blanket module for ITER: Impact of the structural material grade on the neutronic responses von Vella, G., Aiello, G., Fütterer, M.A., Giancarli, L., Oliveri, E., Tavassoli, F.

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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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