Search Results - "Tabarés, F. L."

Electron-induced secondary electron emission coefficient of lithium, tungsten and stainless steel surfaces exposed to low-pressure plasmas by Oyarzabal, E., Martin-Rojo, A.B., Tabarés, F.L.

“…The secondary electron emission (SEE) coefficient by electron impact of Li, W and stainless steel (SS) surfaces exposed to a glow discharge is evaluated and…”
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Physics and Technology Research for Liquid-Metal Divertor Development, Focused on a Tin-Capillary Porous System Solution, at the OLMAT High Heat-Flux Facility by de Castro, A., Oyarzábal, E., Alegre, D., Tafalla, D., González, M., McCarthy, K. J., Scholte, J. G. A., Morgan, T. W., Tabarés, F. L.

“…The operation of the Optimization of Liquid Metal Advanced Targets (OLMAT) facility began in April 2021 with the scientific objective of exposing liquid-metal…”
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Design and Testing of Advanced Liquid Metal Targets for DEMO Divertor: The OLMAT Project by Alegre, D., Oyarzabal, E., Tafalla, D., Liniers, M., Soleto, A., Tabarés, F. L.

“…In a future fusion reactor like DEMOnstration reactor (DEMO) one of the main concerns is the handling of the power exhaust from the plasma, especially at the…”
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Laboratory experiments of uptake and release of hydrogen isotopes in liquid lithium by Oyarzabal, E., Martin-Rojo, A.B., Tabarés, F.L.

“…Laboratory studies of hydrogen and deuterium retention/desorption and hydride formation in liquid lithium samples exposed to those gases at 200°C and 400°C are…”
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Laboratory studies of H retention and LiH formation in liquid lithium by Martín-Rojo, A.B., Oyarzabal, E., Tabarés, F.L.

“…•Absorption and thermal desorption experiments of hydrogen isotopes in liquid lithium have been performed at exposure temperatures up to 400°C.•The kinetics of…”
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Comparative studies of liquid metals for an alternative divertor target in a fusion reactor by Tabarés, F L, Oyarzabal, E, Tafalla, D, Martin-Rojo, A B, Pastor, I, Ochando, M A, Medina, F, Zurro, B, McCarthy, K J

“…Two liquid metals (LM), Li and LiSn (20:80 at), presently considered as alternative materials for the divertor target of a fusion reactor, have been exposed to…”
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Analysis of LiSn alloy at several depths using LIBS by Suchoňová, M., Krištof, J., Pribula, M., Veis, M., Tabarés, F.L., Veis, P.

“…The difference between the composition of the surface and the inner part of the LiSn sample was studied using Calibration Free Laser Induced Breakdown…”
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Behavior of liquid Li-Sn alloy as plasma facing material on ISTTOK by Loureiro, J.P.S., Tabarés, F.L., Fernandes, H., Silva, C., Gomes, R., Alves, E., Mateus, R., Pereira, T., Alves, H., Figueiredo, H.

“…The high power loads impinging on the first wall and particularly the divertor of fusion reactors is a decisive factor to the success of nuclear fusion. An…”
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Impact of lithium-coated walls on plasma performance in the TJ-II stellarator by Sánchez, J., Tabarés, F.L., Tafalla, D., Ferreira, J.A., García-Cortés, I., Hidalgo, C., Medina, F., Ochando, M.A., Pedrosa, M.A.

“…Lithiumization in the TJ-II heliac has been recently performed by vacuum evaporation of metallic Li. Compared to previous wall coating scenarios, an enhanced…”
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Suppression of tritium retention in remote areas of ITER by nonperturbative reactive gas injection by Tabarés, F L, Ferreira, J A, Ramos, A, van Rooij, G, Westerhout, J, Al, R, Rapp, J, Drenik, A, Mozetic, M

“…A technique based on reactive gas injection in the afterglow region of the divertor plasma is proposed for the suppression of tritium-carbon codeposits in…”
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Hydrogen retention studies on lithiated tungsten exposed to glow discharge plasmas under varying lithiation environments using Thermal Desorption Spectroscopy and mass spectrometry by de Castro, A., Valson, P., Tabarés, F.L.

“…For the design of a Fusion Reactor based on a liquid lithium divertor target and a tungsten first wall at high temperature, the interaction of the wall…”
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Comparative studies of H absorption/desorption kinetics and evaporation of liquid lithium in different porous systems and free surfaces by Oyarzabal, E., Martín-Rojo, A.B., Tabarés, F.L.

“…In the present work, a study of the two most relevant properties of liquid lithium with respect to its suitability as a Plasma Facing Component (PFC) element…”
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Optimization of non-oxidative carbon-removal techniques by nitrogen-containing plasmas by Ferreira, J.A., Tabarés, F.L., Tafalla, D.

“…The continuous control of tritium inventory in ITER calls for the development of new conditioning techniques [G. Federici et al., Nucl. Fus. 41 (2001) 1967]…”
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Removal of carbon films by oxidation in narrow gaps: Thermo-oxidation and plasma-assisted studies by Tanarro, I., Ferreira, J.A., Herrero, V.J., Tabarés, F.L., Gómez-Aleixandre, C.

“…The removal of hard amorphous hydrogenated carbon (a-C:H) films from narrow gaps simulating the macro-brush structures present in controlled fusion devices has…”
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Exposure of liquid lithium confined in a capillary structure to high plasma fluxes in PILOT-PSI—Influence of temperature on D retention by Martin-Rojo, A.B., Oyarzabal, E., Morgan, T.W., Tabarés, F.L.

“…Experiments on deuterium retention on liquid lithium confined in a capillary structure followed by ex-situ thermal desorption spectrometry (TDS) at high plasma…”
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Alternative cleaning technique for the removal of carbon deposits by Ferreira, J.A., Tabarés, F.L., Tafalla, D.

“…High efficiency for the removal of carbon coatings in narrow (1mm) gaps and carbon films directly exposed has been found in He/O2 discharges, corresponding to…”
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Anomalous secondary electron emission of metallic surfaces exposed to a Glow Discharge plasma by Oyarzabal, E., Martín-Rojo, A.B., Ferreira, J.A., Tafalla, D., Tabarés, F.L.

“…Secondary electron emission (SEE) yields, γ, of Li, stainless steel (SS) and W surfaces immersed in a He Direct Current Glow Discharge (dc-GD) Plasma have been…”
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Recycling and sputtering studies in hydrogen and helium plasmas under lithiated walls in TJ-II by Tafalla, D., Tabarés, F.L., Ferreira, J.A., Oyarzabal, E., Martín-Rojo, A.B.

“…Lithium sputtering has been studied in TJ-II under lithiated walls. The measured sputtering yield in H plasmas was found to be significantly lower than that…”
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Tritium control techniques in ITER by ammonia injection by Tabarés, F.L., Ferreira, J.A., Ramos, A., Alegre, D., van Rooij, G., Westerhout, J., Al, R., Rapp, J., Drenik, A., Mozetic, M.

“…A technique based on ammonia injection in the afterglow region of the divertor plasma is proposed for the inhibition of tritium/carbon co-deposits in remote…”
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Liquid surfaces for fusion plasma facing components—A critical review. Part I: Physics and PSI by Nygren, R.E., Tabarés, F.L.

“…•Review of worldwide work how on Li, Sn-Li and Ga surfaces affects the plasma edge, 108 references.•Summary of research being done in confinement facilities…”
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