Search Results - "Fütterer, M.A"

HTR-PM fuel pebble irradiation qualification in the high flux reactor in Petten by 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

“…NRG has performed a High Temperature Reactor fuel qualification test in the framework of the Chinese HTR development for INET – Tsinghua University, as a part…”
Get full text

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

“…The European HTR R&D project ARCHER (Advanced High-Temperature Reactors for Cogeneration of Heat and Electricity R&D) builds on a solid HTR technology…”
Get full text

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

“…The breeding blanket is an essential in-vessel component for fusion power plants based on the deuterium–tritium fuel. It is submitted to severe operating…”
Get full text

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

“…The hydrogen isotope transport through the first wall between plasma and first wall coolant has been investigated. The time dependence of hydrogen isotope…”
Get full text

On the use of tin–lithium alloys as breeder material for blankets of fusion power plants by Fütterer, M.A, Aiello, G, Barbier, F, Giancarli, L, Poitevin, Y, Sardain, P, Szczepanski, J, Li Puma, A, Ruvutuso, G, Vella, G

“…Tin–lithium alloys have several attractive thermo-physical properties, in particular high thermal conductivity and heat capacity, that make them potentially…”
Get full text

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

“…The water-cooled lithium–lead (WCLL) DEMO blanket is one of the two European blanket lines to be further developed with the aim, in the short term, of…”
Get full text

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

“…During irradiation tests at high temperature failure of commercial Inconel 600 sheathed thermocouples is commonly encountered. As instrumentation, in…”
Get full text

Generation IV Reactor Safety and Materials Research by the Institute for Energy and Transport at the European Commission's Joint Research Centre by 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.

“…To support the drafting, development, implementation and monitoring of European energy and transport policy, the Institute for Energy and Transport of the…”
Get full text

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

“…For HTR fuel irradiation tests in the HFR Petten a specific installation was designed and installed, dubbed the “Sweep Loop Facility” (SLF). The SLF is tasked…”
Get full text

EUROPAIRS: The European project on coupling of High Temperature Reactors with industrial processes by 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.

“…Developers of High Temperature Reactors (HTR) worldwide acknowledge that the main asset for market breakthrough is its unique ability to address growing needs…”
Get full text

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

“…Knowledge of the TRISO particle distributions inside HTR fuel pebbles or compacts may help manufacturers to improve the quality of their fuel by providing…”
Get full text

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

“…As early as the 1970s, attempts were made to reduce the peak fuel temperature by means of so-called “wallpaper fuel”, in which the fuel is arranged in a…”
Get full text

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

“…There is a substantial market for nuclear energy in non-electric applications such as hydrogen production or water desalination. Among the Generation IV…”
Get full text

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

“…In this paper, we present computations linking the tritium release rate to the characteristics of lithium–lead and helium cooling circuits. Impacting component…”
Get full text

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

“…Numerical modelling has been successfully applied during the design and evaluation of the HFREU1bis HTR fuel pebble irradiation experiment conducted by the…”
Get full text

In-pile tritium-permeation measurements on T91 tubes with double walls or a Fe–Al/Al 2O 3 coating by Conrad, R, Bakker, K, Chabrol, C, Fütterer, M.A, van der Laan, J.G, Rigal, E, Stijkel, M.P

“…Two new irradiation projects are being performed at the HFR Petten, named EXOTIC-8.9 and EXOTIC-8.10. Issues such as tritium release from candidate ceramic…”
Get full text

In-pile tritium-permeation measurements on T91 tubes with double walls or a Fe–Al/Al2O3 coating by Conrad, R, Bakker, K, Chabrol, C, Fütterer, M.A, van der Laan, J.G, Rigal, E, Stijkel, M.P

Get full text

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

“…The deuterium and tritium re-emission fluxes from the first wall (FW) of the DEMO reactor have been calculated. The influence of temperature of the first wall…”
Get full text

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

“…Blankets and divertors are the key components of a fusion power plant due to their large impact on the overall plant design, performance and availability, and…”
Get full text

Further improvements of the water-cooled Pb–17Li blanket by Fütterer, M.A, Benamati, G, Ricapito, I, Giancarli, L, Le Marois, G, Li Puma, A, Poitevin, Y, Reimann, J, Salavy, J.-F, Szczepanski, J, Vella, G, Ruvutuso, G

“…The water-cooled lithium–lead (WCLL) blanket is based on reduced-activation ferritic–martensitic steel as the structural material, the liquid alloy Pb–17Li as…”
Get full text