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Author

G. Aiello

Bio: G. Aiello is an academic researcher from University of Palermo. The author has contributed to research in topics: Blanket & Heat flux. The author has an hindex of 5, co-authored 6 publications receiving 266 citations.
Topics: Blanket, Heat flux, Neutron source, Divertor, Coolant

Papers
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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: The main features of recent fusion reactor blanket conceptual designs using SiC f /SiC as structural material are presented in this article, with particular attention paid to the adopted safety and maintenance strategy.

35 citations

Journal ArticleDOI
TL;DR: In this paper, the use of low activation Ceramic matrix composites (CMCs) appears as the most promising solution to obtain high safety standards in future fusion power reactors.

18 citations

Journal ArticleDOI
TL;DR: In this article, the authors recall the main features of the TAURO blanket, a self-cooled Pb-17Li concept using SiC f /SiC composite as structural material, and describe the most recent thermo-mechanical analyses performed on the blanket.

17 citations

Journal ArticleDOI
TL;DR: In this paper, the results of a neutronic and photonic analysis of the single box concept is presented, including the whole assembly and many of the DEMO reactor components, together with a three-dimensional neutron source.

8 citations


Cited by
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Journal ArticleDOI
01 Apr 1988-Nature
TL;DR: In this paper, a sedimentological core and petrographic characterisation of samples from eleven boreholes from the Lower Carboniferous of Bowland Basin (Northwest England) is presented.
Abstract: Deposits of clastic carbonate-dominated (calciclastic) sedimentary slope systems in the rock record have been identified mostly as linearly-consistent carbonate apron deposits, even though most ancient clastic carbonate slope deposits fit the submarine fan systems better. Calciclastic submarine fans are consequently rarely described and are poorly understood. Subsequently, very little is known especially in mud-dominated calciclastic submarine fan systems. Presented in this study are a sedimentological core and petrographic characterisation of samples from eleven boreholes from the Lower Carboniferous of Bowland Basin (Northwest England) that reveals a >250 m thick calciturbidite complex deposited in a calciclastic submarine fan setting. Seven facies are recognised from core and thin section characterisation and are grouped into three carbonate turbidite sequences. They include: 1) Calciturbidites, comprising mostly of highto low-density, wavy-laminated bioclast-rich facies; 2) low-density densite mudstones which are characterised by planar laminated and unlaminated muddominated facies; and 3) Calcidebrites which are muddy or hyper-concentrated debrisflow deposits occurring as poorly-sorted, chaotic, mud-supported floatstones. These

9,929 citations

Journal ArticleDOI
TL;DR: In this article, a summary of the properties of SiC/SiC composites with chemically vapor-infiltrated (CVI) SiC matrices is presented.

374 citations

Journal ArticleDOI
TL;DR: In this paper, the authors review the development, characterization, and irradiation effect studies for SiC composites for fusion energy applications and make the case that SiC composite are progressing from the stage of potential viability and proof-of-principle to one where they are ready for system demonstration, i.e., for flow channel inserts in Pb-Li blankets.

322 citations

Journal ArticleDOI
TL;DR: In this article, the results of inventory burn-up calculations on pure W and quantitative estimates for He production rates in both a fusion-reactor environment and under conditions expected in the ITER experimental device are presented.
Abstract: W and W-alloys are among the primary candidate materials for plasma-facing components in the design of fusion reactors, particularly in high-heat-flux regions such as the divertor. Under neutron irradiation W undergoes transmutation to its near-neighbours in the periodic table. Additionally He and H are particles emitted from certain neutron-induced reactions, and this is particularly significant in fusion research since the presence of helium in a material can cause both swelling and a strong increase in brittleness. This paper presents the results of inventory burn-up calculations on pure W and gives quantitative estimates for He production rates in both a fusion-reactor environment and under conditions expected in the ITER experimental device. Transmutation reactions in possible alloying elements (Re, Ta, Ti and V), which could be used to reduce the brittleness of pure W, are also considered. Additionally, for comparison, the transmutation of other fusion-relevant materials, including Fe and SiC, are presented.

286 citations