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Author

M.A Fütterer

Bio: M.A Fütterer is an academic researcher from French Alternative Energies and Atomic Energy Commission. The author has contributed to research in topics: Blanket & Coolant. The author has an hindex of 13, co-authored 32 publications receiving 426 citations.
Topics: Blanket, Coolant, Cogeneration, Divertor, Permeation

Papers
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Journal ArticleDOI
TL;DR: In this article, the authors present computations linking the tritium release rate to the characteristics of lithium-lead and helium cooling circuits, and evaluate the impact of these components on their performance.

48 citations

Journal ArticleDOI
TL;DR: An update on the international effort in the development of the Very High Temperature Reactor system pursued through international collaboration in the Generation IV International Forum (GIF) and an outlook for further activities are provided.

44 citations

Journal ArticleDOI
TL;DR: In this article, the hydrogen isotope transport through the first wall between plasma and first wall coolant has been investigated and the time dependence of hydrogen-isotope permeation from plasma into water cooling has been calculated.

35 citations

Journal ArticleDOI
TL;DR: In this article, the tritium leakage due to the permeation through the main structural materials constitutes one of the main problems of the fusion technology, and the influence of temperature gradient, surface conditions, isotopic effect, and trapping in ion-and neutron-induced defects on the hydrogen isotope permeation and inventory has been considered.

29 citations

Journal ArticleDOI
L. Giancarli, Gianluca Benamati1, M.A Fütterer, G. Marbach, C. Nardi1, J Reimann 
TL;DR: In this article, a preliminary design of the test module and of the associated circuit components to be tested in ITER has been performed taking into account ITER specifications for test ports and ITER pulsed working conditions.

28 citations


Cited by
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Journal ArticleDOI
TL;DR: A review of the hydrogen permeation barriers which can be applied to the structural metals used in fusion power plants is presented in this article, where the need for barriers appears strongest in Pb-17Li blanket designs, although barriers are also necessary for other blanket and coolant systems.

234 citations

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TL;DR: In this paper, the authors summarized the top technical issues and elucidates the primary challenges in developing the blanket/first wall and identified the key R&D needs in non-fusion and fusion facilities on the path to DEMO.

234 citations

Journal ArticleDOI
TL;DR: In this paper, a review of hydrogen isotope retention and migration in tungsten (W) is presented, where a large scatter of the deuterium (D) retention database is used to clarify the mechanism of hydrogen inventory in W. Several points are reviewed: (i) inventory in pure W, (ii) inventory of W pre-implanted by carbon ions, and (iii) inventory inventory in Tungsten oxide.

232 citations

Journal ArticleDOI
TL;DR: The SiCf/SiC composite is a promising structural material candidate for fusion power cores and has been considered internationally in several power plant studies as discussed by the authors, but its behavior and performance at high temperatures and under irradiation are still not well known and need to be better characterized.

192 citations

Journal ArticleDOI
TL;DR: In this paper, a dual functional lithium-lead (DFLL) test blanket module (TBM) concept has been proposed for testing in the International Thermonuclear Experimental Reactor (ITER) and the Experimental Advanced Superconducting Tokamak (EAST) in China to demonstrate the technologies of the liquid lithium−lead breeder blankets with emphasis on the balance between the risks and the potential attractiveness of blanket technology development.
Abstract: A dual functional lithium–lead (DFLL) test blanket module (TBM) concept has been proposed for testing in the International Thermonuclear Experimental Reactor (ITER) and the Experimental Advanced Superconducting Tokamak (EAST) in China to demonstrate the technologies of the liquid lithium–lead breeder blankets with emphasis on the balance between the risks and the potential attractiveness of blanket technology development. The design of DFLL-TBM concept has the flexibility of testing both the helium-cooled quasi-static lithium–lead (SLL) blanket concept and the He/PbLi dual-cooled lithium–lead (DLL) blanket concept. This paper presents an effective testing strategy proposed to achieve the testing target of SLL and DLL DEMO blankets relevant conditions, which includes three parts: materials R&D and small-scale out-of-pile mockups testing in loops, middle-scale TBMs pre-testing in EAST and full-scale consecutive TBMs testing corresponding to different operation phases of ITER during the first 10 years. The design of the DFLL-TBM concept and the testing strategy ability to test TBMs for both blanket concepts in sequence and or in parallel for both ITER and EAST are discussed.

191 citations