Title of article
Ti3SiC2 as a candidate material for lead cooled fast reactor
Author/Authors
Utili، نويسنده , , M. and Agostini، نويسنده , , M. and Coccoluto، نويسنده , , G. and Lorenzini، نويسنده , , E.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2011
Pages
6
From page
1295
To page
1300
Abstract
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 Ti3SiC2 is that it combines some of the most attractive proprieties of ceramics with those of metals.
aterial 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 10−6 wt% in the melt), with an average temperature of 500 °C and a stream velocity of about 1 m/s.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2011
Journal title
Nuclear Engineering and Design Eslah
Record number
1590672
Link To Document