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41.
P Castrucci M Diociaiuti CM Tank S Casciardi F Tombolini M Scarselli M De Crescenzi VL Mathe SV Bhoraskar 《Nanoscale》2012,4(16):5195-5201
We report on the characteristics of a new class of Si-based nanotubes and spherical nanoparticles synthesized by the dc-arc plasma method in a mixture of argon and hydrogen. These two nanostructures share common properties: they are hollow and possess very thin, highly polycrystalline and mainly oxidized walls. In particular, we get several hints indicating that their walls could constitute only one single Si oxidized layer. Moreover, we find that only the less oxidized nanotubes exhibit locally atomic ordered, snakeskin-like areas which possess a hexagonal arrangement which can be interpreted either as an sp(2) or sp(3) hybridized Si or Si-H layer. Their ability to not react with oxygen seems to suggest the presence of sp(2) configuration or the formation of silicon-hydrogen bonding. 相似文献
42.
Luca Camilli Manuela Scarselli Silvano Del Gobbo Paola Castrucci Francesca Romana Lamastra Francesca Nanni Eric Gautron Serge Lefrant Franco D’Orazio Franco Lucari Maurizio De Crescenzi 《Carbon》2012,50(2):718-721
Multiwalled carbon nanotubes synthesized directly on austenitic stainless steel result in being filled with pure iron nanoparticles. X-ray diffraction shows that the nanoparticles are either in the γ- or α-phase, although iron in the original alloy is in γ-phase because of the presence of nickel. This phase transformation is due to the selective extraction of iron, performed by carbon nanotubes during their growth. A high coercivity of iron-filled carbon nanotubes is measured although the starting steel is paramagnetic. The presence of the α-phase, the magnetic anisotropy and the single domain character of the Fe nanoparticles explain their magnetic behavior. 相似文献
43.
Manuela Scarselli Luca Camilli Paola Castrucci Francesca Nanni Silvano Del Gobbo Eric Gautron Serge Lefrant Maurizio De Crescenzi 《Carbon》2012,50(3):875-884
A simple method to decorate multiwalled carbon nanotubes (MWCNTs) with Au, Ag and Cu nanoparticles is illustrated. The method consists in directly depositing the selected metals by thermal evaporation on the carbon nanotubes. Comparative measurements carried out on samples that differ in the quantity and type of the deposited metal, reveal that isolated discrete particles form on the nanotube outer wall for all three metals. The CNT-based composites have been investigated by scanning and transmission electron microscopy to determine the size, shape and distribution of the nanoparticles. The results indicate that the quantity of evaporated metal only affects the nanoparticle size and not the average particle density. Particle composition was determined by X-ray photoelectron spectroscopy study. The results are discussed in terms of metal nanoparticle–tube interactions, an important issue for the fundamental and practical applications of similar MWCNT based composites. 相似文献
44.
45.
Eliseo Visca Pietro Agostini Fabio Crescenzi A. Malavasi Aldo Pizzuto Paolo Rossi Sandro Storai Marco Utili 《Fusion Engineering and Design》2012,87(7-8):941-945
The development of a divertor concept for fusion power plants that is able to grant efficient recovery and conversion of the considerable fraction (~15%) of the total fusion thermal power incident is deemed to be an urgent task to meet in the EU Fast Track scenario. The He-cooled conceptual divertor design is one of the possible candidates. Helium cooling offers several advantages including chemical and neutronic inertness and the ability to operate at higher temperatures and lower pressures than those required for water cooling. The HETS (high-efficiency thermal shield) concept, initially developed by ENEA for water, has been adapted for use with He as coolant. This DEMO divertor concept is based on elements joined in series and protected by a hemispheric dome; it allows an increase of thermal exchange coefficient both for high speed of gas and for “jet impingement” effects of gas coming out from the internal side of hemispheric dome. It has been calculated to be capable of sustaining an incident heat flux of 10 MW/m2 when operating at 10 MPa, an inlet He temperature of 600 °C, and an outlet temperature of 800 °C. The presented activity, performed in the frame of EFDA-TW5TRP-001 task, was focused on the manufacturing of a single HETS module and on its thermal–hydraulic testing. The materials used for the HETS module manufacturing were all DEMO-compatible: W for the armor material and the hemispherical-dome, DENSIMET for the exchanger body. The testing is performed by connecting the module to HEFUS3 He loop system that is a facility able to supply the He flow to the required testing conditions: 400 °C, 4–8 MPa and 20–40 g/s. The needed incident heat flux is obtained by RF inducting equipment coupled to an inductor coil installed just over the HETS module. A CFD analysis by ANSYS-CFX was performed in order to predict the thermal–mechanical behavior of the module and a final comparison with the experimental data is required to validate the CFD results. All parameters are monitored and recorded by data acquisition system. 相似文献
46.
47.
Grammars have exceptions 总被引:9,自引:0,他引:9
48.
F. Crisanti A. Cucchiaro R. Albanese G. Artaserse M. Baruzzo T. Bolzonella G. Brolatti G. Calabrò F. Crescenzi R. Coletti P. Costa A. della Corte A. Di Zenobio P. Frosi D. Harting L. Lauro Taroni G. Maddaluno D. Marcuzzi F. Maviglia L. Muzzi S. Wiesen 《Fusion Engineering and Design》2011,86(6-8):497-503
Fusion Advanced Studies Torus (FAST) aims to contribute to the exploitation of ITER and to explore innovative DEMO technology. FAST has been designed to study, in an integrated scenario: (a) relevant plasma-wall interaction problems, with a large power load (P/R ~ 22 MW/m; P/R2 ~ 12 MW/m2) and with a full metallic wall; (b) to tackle operational problems in regimes with relevant fusion parameters; (c) to investigate the non-linear dynamics of fast particles (alpha like) in burning plasmas. FAST will operate on a wide parameters range, namely in high performance H-mode (BT ~ 8.5 T; IP ~ 8 MA) as well as in advanced Tokamak operation up to full non-inductive current scenario (IP ~ 2 MA). The main heating is based on 30 MW ICRH, but the ports have been designed to allocate up to 20 MW of 1 MeV NNBI. Helium gas at 30 K is used for cooling of the full machine, a preliminary analysis shows the possibility of realizing FAST with a complete superconductor set of coils. An innovative active system is under development to reduce and to control the magnetic ripple. Tungsten (W) or liquid lithium (L–Li) has been chosen for the divertor material plates and the code EDGE2D has been used to optimize the divertor geometry. 相似文献
49.
Pilu Crescenzi Andrea Marino Gianluca Rossi Paola Vocca 《Information Processing Letters》2011,111(5):239-246
In this paper, we study the stationary node distribution of a variation of the Random Waypoint mobility model, in which nodes move in a smooth way following one randomly chosen Manhattan path connecting two points. We provide analytical results for the spatial node stationary distribution of this model. As an application, we exploit this result to derive an upper bound on the transmission range of the nodes of a MANET, moving according to this model, that guarantees the connectivity of the communication graph with high probability. 相似文献
50.
A. Cucchiaro G. Brolatti G. Calabrò V. Cocilovo P. Frosi F. Crescenzi F. Crisanti G. Maddaluno V. Pericoli-Ridolfini A. Pizzuto C. Rita G. Ramogida S. Roccella P. Rossi 《Fusion Engineering and Design》2011,86(6-8):703-707
FAST (Fusion Advanced Studies Torus) is a proposal for a Satellite Facility which can contribute the rapid exploitation of ITER and prepare ITER and DEMO regimes of operation, as well as exploit innovative plasma facing component systems for DEMO. FAST is a compact (Ro = 1.82 m, a = 0.64 m, triangularity δ = 0.4) and cost effective machine able to investigate, with integration capability, non linear dynamics effects of alpha particle behaviour in burning plasmas. FAST operates in high performance H-mode (BT up to 8.5 T; IP up to 8 MA), as well as in advanced tokamak mode (IP = 3 MA), and in full non inductive current mode (IP = 2 MA). Helium gas at 30 K is used for cooling the resistive copper magnets. This allows for a pulse duration up to 170 s at 3 MA/3.5 T. The vacuum vessel (VV), segmented into 20-degree modules, is capable to accommodate a 40 MW RF power system. The machine has been designed to house a 10 MW Negative Neutral Beam Injection (NNBI) system. Tungsten (W) or liquid lithium (L-Li) have been chosen as the divertor plate materials, and argon or neon as the impurities to be injected for mitigating the thermal loads. 相似文献