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F. Scaffidi-Argentina

Bio: F. Scaffidi-Argentina is an academic researcher. The author has contributed to research in topics: BET theory & Reactivity (chemistry). The author has an hindex of 3, co-authored 3 publications receiving 25 citations.

Papers
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TL;DR: In this paper, the results of chemical reactivity experiments for Be pebbles (2-mm and 0.2mm diameter) and Be powder (14-31 pm diameter) exposed to steam at elevated temperatures were reported.
Abstract: This paper reports the results of chemical reactivity experiments for Be pebbles (2-mm and 0.2-mm diameter) and Be powder (14-31 pm diameter) exposed to steam at elevated temperatures, 350 to 900°C for pebbles and 400 to 500°C for powders. We measured BET specific surface areas of 0.12 m 2 /g for 2-mm pebbles, 0.24 m 2 /g for 0.2-mm pebbles and 0.66 to 1.21 m 2 /g for Be powder samples. These experiments showed a complex reactivity behavior for the material, dependent primarily on the test temperature. Average H 2 generation rates for powder samples, based on measured BET surface areas, were in good agreement with previous measurements for fully-dense CPM-Be. Rates for the Be pebbles, based on measured BET surface areas, were systematically lower than the CPM-Be rates, possibly because of different surface and bulk features for the pebbles, especially surface-layer impurities, that contribute to the measured BET surface area and influence the oxidation process at the material surface.

10 citations

Journal ArticleDOI
TL;DR: In this article, the results of chemical reactivity experiments for Be pebbles (2 and 0.2 mm diameter) and Be powder (14-31 μm diameter) exposed to steam at elevated temperatures, 350-900°C for Pebbles and 400-500 °C for powders, were reported.

9 citations

Journal ArticleDOI
TL;DR: In this paper, steam chemical reactivity experiments were conducted for several ITER-like tokamak plasma-facing component (PFC) materials: NB31 and NS31 carbon fiber composites (CFCs), W-1%La, DShG-200 Be, and Be (S65C and Kawecki PO Ductile Be) specimens irradiated to fast neutron fluences ranging from 5×1019 to 1×1021 n/cm2.

7 citations


Cited by
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TL;DR: In this article, the authors review the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next-step fusion reactors.
Abstract: The major increase in discharge duration and plasma energy in a next step DT fusion reactor will give rise to important plasma-material effects that will critically influence its operation, safety and performance. Erosion will increase to a scale of several centimetres from being barely measurable at a micron scale in today's tokamaks. Tritium co-deposited with carbon will strongly affect the operation of machines with carbon plasma facing components. Controlling plasma-wall interactions is critical to achieving high performance in present day tokamaks, and this is likely to continue to be the case in the approach to practical fusion reactors. Recognition of the important consequences of these phenomena stimulated an internationally co-ordinated effort in the field of plasma-surface interactions supporting the Engineering Design Activities of the International Thermonuclear Experimental Reactor project (ITER), and significant progress has been made in better understanding these issues. The paper reviews the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next step fusion reactors. Two main topical groups of interaction are considered: (i) erosion/redeposition from plasma sputtering and disruptions, including dust and flake generation and (ii) tritium retention and removal. The use of modelling tools to interpret the experimental results and make projections for conditions expected in future devices is explained. Outstanding technical issues and specific recommendations on potential R&D avenues for their resolution are presented.

1,187 citations

Journal ArticleDOI
TL;DR: In this article, the authors investigated the oxidative erosion of seven types of graphite by heating in air at temperatures between 600 and 1000 K. The specimens include pyrolytic graphite, fine-grain graphites, carbon-fibre composites (CFC), and graphites doped with Si and Ti.

43 citations

Journal ArticleDOI
TL;DR: In this article, the principal types of materials that have some role in safety are recalled, which either represent a potential source of hazard or contribute to the amelioration of hazards; in each case the related issues are reviewed.
Abstract: Fusion power holds the promise of electricity production with a high degree of safety and low environmental impact. Favourable characteristics of fusion as an energy source provide the potential for this very good safety and environmental performance. But to fully realize the potential, attention must be paid in the design of a demonstration fusion power plant (DEMO) or a commercial power plant to minimize the radiological hazards. These hazards arise principally from the inventory of tritium and from materials that become activated by neutrons from the plasma. The confinement of these radioactive substances, and prevention of radiation exposure, are the primary goals of the safety approach for fusion, in order to minimize the potential for harm to personnel, the public, and the environment. The safety functions that are implemented in the design to achieve these goals are dependent on the performance of a range of materials. Degradation of the properties of materials can lead to challenges to key safety functions such as confinement. In this paper the principal types of material that have some role in safety are recalled. These either represent a potential source of hazard or contribute to the amelioration of hazards; in each case the related issues are reviewed. The resolution of these issues lead, in some instances, to requirements on materials specifications or to limits on their performance.

33 citations

Journal ArticleDOI
TL;DR: The technical challenges resulting from the choice of water coolant and the differences in approach and assumptions that lead to different design decisions amongst researchers in this field are summarized.

25 citations

Journal ArticleDOI
TL;DR: A synthesis of the work that has been performed on ASTEC as part of its adaptation to fusion ITER facility, in particular concerning the development of some specific models, the state of validation of the code and some first calculations for accident transients considered in the basis design are presented.

18 citations