M. Utili, M. Agostini, G. Coccoluto, E. Lorenzini

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One of the main issues regarding the design of LFR is the corrosion-erosion behaviour of materials in contact with high temperature and high velocity lead, such as pump impeller and bearing materials. Those materials will worked in lead at about 480 °C with a velocity relative to impeller blade in the magnitude of 10 m/s. Ti3SiC2, a ternary compound was selected as one of the most promising candidate material, the most significant aspect of Ti3SiC2is that it combines some of the most attractive proprieties of ceramics with those of metals. This material was already applied in industry but more effort is needed to qualify its performance when compared with candidate structural stainless steel available in Europe. With the purpose of evaluating the corrosion resistance of Ti3SiC2, a preliminary screening test was carried out at ENEA Brasimone in fluent lead under oxidation conditions (oxygen concentration of about 10-6wt% in the melt), with an average temperature of 500 °C and a stream velocity of about 1 m/s. © 2010 Elsevier B.V. All rights reserved.
Original languageEnglish
Pages (from-to)1295 - 1300
Number of pages6
JournalNuclear Engineering and Design
Issue number5
Publication statusPublished - May 2011
Externally publishedYes


All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Safety, Risk, Reliability and Quality
  • Waste Management and Disposal
  • Mechanical Engineering

Cite this

Utili, M., Agostini, M., Coccoluto, G., & Lorenzini, E. (2011). Ti. Nuclear Engineering and Design, 241(5), 1295 - 1300. https://doi.org/10.1016/j.nucengdes.2010.07.038