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3 results on '"Luciano Pilloni"'

1. Early failure of a locked titanium plate in a proximal humeral fracture: Case report and metallurgic analysis

Author

Giandomenico Logroscino, Fabrizio Donati, Michela Saracco, Luciano Pilloni, and Corrado Piconi

Subjects
Surgery, RD1-811
Abstract

Angular stability locking plates are commonly used in proximal humeral fractures, especially in old patients with osteoporotic bones. These implants show good results in short and midterm follow-up, but complications are not uncommon. Here we present a case report to describe a case of early failure of a proximal angular stability plate implanted in a 72 years old female with a highly unstable two part proximal humeral fracture. An optical and metallurgic analysis was also conducted to study the modalities of failure. We concluded that anatomic reduction and restoration of the medial cortical support are crucial in order to minimize the mechanical load on the bone–metal interface and to prevent mechanical failure, in particular when the fracture rim drop in the weak point of the plate that was found in the proximal two symmetric holes (Holes E). Keywords: Proximal humerus fracture, Plate failure, Angular stability locking plate, Metallurgic plate analysis

Published
2018
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2. Development of innovative materials and thermal treatments for DEMO water cooled blanket

Author

L. Bozzetto, C. Cristalli, Luciano Pilloni, N. Bettocchi, O. Tassa, E. Zanin, Pilloni, L., Cristalli, C., Tassa, O., Bozzetto, L., Zanin, E., and Bettocchi, N.

Subjects
Nuclear and High Energy Physics, Toughness, Materials science, Materials Science (miscellaneous), Charpy impact test, Blanket, 01 natural sciences, Heat treatment, 010305 fluids & plasmas, 0103 physical sciences, Ultimate tensile strength, Tensile, Irradiation, Charpy, Embrittlement, Microstructure, 010302 applied physics, EUROFER 97, KLST, RAFM steels, Metallurgy, lcsh:TK9001-9401, Grain size, Nuclear Energy and Engineering, RAFM steel, lcsh:Nuclear engineering. Atomic power
Abstract

One of the options currently taken into account for the realization of the first DEMO reactor is the “water-cooled lanket”. This option implies an irradiation temperature for the blanket material in the range of 280–350 °C. Therefore, in light of the under irradiation behaviour of EUROFER, namely of the DBTT shift toward high temperature due to the low irradiation temperature embrittlement, the target of the hereby reported activities is the development of much tougher alloys, to try to tolerate the embrittlement due to the low irradiation temperature. We report in this paper the work done to optimize the toughness of Eurofer 97, increasing the normalizing temperature and maintaining a small grain size using multiple normalizing treatments. We report also the mechanical behaviour of two 9Cr1WTa type alloys, produced and tested with the same aim to find alloys more resistant to embrittlement at low irradiation temperature. Keywords: EUROFER 97, RAFM steels, Microstructure, Heat treatment, Tensile, Charpy, KLST

Published
2019

3. Grain size reduction strategies on Eurofer

Author

I. Salvatori, Luciano Pilloni, C. Cristalli, S. Storai, O. Tassa, Storai, S., Cristalli, C., and Pilloni, L.

Subjects
Nuclear and High Energy Physics, Toughness, Materials science, Multiple normalization, Materials Science (miscellaneous), 01 natural sciences, 010305 fluids & plasmas, Brittleness, Microstructure, Recrystallization, EUROFER 97, RAFM steels, KLST, Asymmetric rolling, 0103 physical sciences, Tempering, Embrittlement, Strengthening mechanisms of materials, 010302 applied physics, Metallurgy, lcsh:TK9001-9401, Grain size, Nuclear Energy and Engineering, RAFM steel, Martensite, lcsh:Nuclear engineering. Atomic power, Grain boundary
Abstract

One of the options currently taken into account for the realization of the first DEMO reactor is the “water-cooled blanket”. This option implies a minimum irradiation temperature for the blanket material in the range of 280–350 °C. In addition to the DBTT (Ductile to Brittle Transition Temperature) shift due to the DPA (displacement per atom) damage under irradiation, also the issue of the increased embrittlement due to He production must be taken into account. This issue appears even more detrimental and less manageable because the DBBT shift due to the Helium production does not saturate with the dose, as it results from previous works reported in literature. The experimental results and the difference in behaviour between ODS (Oxide Dispersion Strengthened Steels) RAFM (Reduced Activation Ferritic Martensitic) and other FM (Ferritic Martensitic) alloys (EM10, P91) showed that it is possible to improve the resistance to He embrittlement by both intra-granular precipitation of Y-Ti oxides and by decreasing the grain size at the same time. Nevertheless, anyway, the multiplication of the grain boundaries increases the dilution of He on grain surface, delaying the formation of He bubbles on grain boundaries and, therefore, the susceptibility to the He embrittlement. Several grain size reduction strategies have then been investigated on EUROFER both at the austenitization stage, on the PAGS (Prior Austenite Grain Size), and at the tempering stage, on the tempered martensite. The microstructural observations have been carried out by means of SEM (Scanning Electron Microscopy). Also the effect of grain size reduction on the toughness of the material will be taken into account; The DBTTs resulting from impact tests on KLST specimens will be shown. The outcomes of the microstructural observations, as well as the preliminary mechanical characterization (impact tests) will be discussed in this paper. Keywords: EUROFER 97, RAFM steels, Microstructure, Multiple normalization, Asymmetric rolling, Recrystallization, KLST

Published
2018

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