Zobrazeno 1 - 10
of 102
pro vyhledávání: '"G Benamati"'
Publikováno v:
Corrosion Science. 50:1672-1683
Corrosion tests of T91 and AISI 316L steels in stagnant Pb–Bi eutectic saturated by oxygen at 500, 520, 540 and 560 °C were carried out. The corrosion mode as a function of temperature was revealed. The oxidation was the main interaction mechanism
Autor:
L. Augustin, M. Querci, M. Armeni, F. Frascati, S. Panichi, C. Arrighi, A. Antonelli, G. Benamati, Eric Lefebvre, S. Nucci
Publikováno v:
Annals of Glaciology. 47:134-140
A new deep drill has been developed within the framework of the European Programme for Ice Coring in Antarctica (EPICA). Several versions of the EPICA drill exist. The version used at Dome Concordia (75˚06'1" S, 123˚23'71" E) was operated with a ne
Publikováno v:
Journal of Nuclear Materials. :1391-1395
Corrosion and tensile samples of the EUROFER 97 steel were exposed to Pb–17Li in the LIFUS II loop at 480 °C. The specimens were extracted after 1500, 3000 and 4500 h exposure. After extraction, weight change measurements and metallurgical analysi
Publikováno v:
Journal of Nuclear Materials. 301:23-27
Compatibility tests on the austenitic AISI 316L and the martensitic MANET II steels in stagnant PbBi were performed at 573, 673 and 823 K with exposures up to 5000 h. The change of the corrosion mechanism with increasing temperature has been evaluate
Publikováno v:
Hyperfine Interactions. :403-408
The corrosion resistance of AISI 316 LN stainless steel was studied in contact with stagnant, oxygen-saturated liquid lead at 749 K for times up to 1200 h. The reaction products were analysed by means of optical and scanning electron microscopy, elec
Publikováno v:
Journal of Nuclear Materials. 296:243-248
The compatibility of steels with liquid lead and liquid lead–bismuth is a critical issue for the development of accelerator-driven system (ADS). In this work the results of a set of preliminary tests carried out in stagnant molten lead at 737 K and
Publikováno v:
Journal of Nuclear Materials. 273:233-238
Results on the fabrication of a tritium permeation barrier by spraying Fe–Cr–Al powders are described. The sprayed coatings were deposited at temperatures below the A c 1 temperature of the ferritic–martensitic steel substrate and no post-depos
Publikováno v:
Journal of Nuclear Materials. :391-395
The development of the water cooled lithium lead (WCLL) DEMO fusion reactor requires the production of a material capable of acting as a tritium permeation barrier (TPB). In the DEMO blanket reactor permeation barriers on the structural material are
Autor:
W Schutz, S. Cevolani, Hiroji Katsuta, G Benamati, Yoshio Kato, H Roehrig, D.L. Smith, Y Miyauchi, L. Green, Thanh Q. Hua, Satoshi Konishi
Publikováno v:
Journal of Nuclear Materials. :388-393
The Conceptual Design Activity (CDA) for the International Fusion Materials Irradiation Facility (IFMIF) has been conducted. For the IFMIF Target Facility, the conceptual designs of the following two main components have been performed. The design co
Publikováno v:
Journal of Nuclear Materials. 245:108-114
A time dependent permeation method is used to measure the permeability, diffusivity and solubility of deuterium in the low activation martensitic steels F82H and Batman. The measurements cover the temperature range from 373 to 743 K which includes th