Abstract
FeCrAl alloy is a promising candidate material for the fourth-generation reactor core cladding material. Adjustment of the Cr content is one of the effective ways to obtain enhanced performance for the FeCrAl alloy. In this work, Fe–xCr–6Al alloy (11 ≤ x ≤ 15) with different Cr content were successfully prepared by hot rolling. When Cr replacement of Fe atoms in Fe–xCr–6Al alloy rises from 11 to 15wt%, the lattice distortion of Fe–xCr–6Al alloy increases, and the mechanical properties and thermal conductivity of the Fe–xCr–6Al alloy are raised. Compared with Al content, Cr content has less effect on Fe–xCr–6Al oxidation resistance.
Highlights
In recent years, with the potential shortage of traditional energy sources, nuclear power has become increasingly important (Farmer et al, 2014)
The microstructure and macroscopic properties of the alloy are often affected by the types and contents of the elements in the alloy
Since the test sample is in a bulk form, the crystal orientation of the samples will affect the absolute strength of X-ray diffraction (XRD) which makes the peak intensities varying from one alloy to another, but impact little on peak position
Summary
With the potential shortage of traditional energy sources, nuclear power has become increasingly important (Farmer et al, 2014). In the nuclear accident at Fukushima Nuclear Power Plant in Japan in 2011, the Zr alloy cladding was rapidly oxidized under the loss of coolant accident (LOCA) conditions at 1,200°C, resulting in damage to the core and a hydrogen explosion (Pint et al, 2015). The oxidation weight gains of commercial zirconium alloy like Zry-4, D4, M5, E110 and Zirlo in 600°C high temperature water vapor are 2–10mg/cm2h during 45h exposure. As the oxidation temperature increases, the oxidation weight gains of commercial zirconium alloy like Zry-4, D4, M5, E110 and Zirlo in 1,200°C high temperature water vapor are 50–80mg/cm2h (Steinbrück et al, 2011). It is difficult to adopt the current commercial Zr alloys as claddings in the fourth-generation nuclear reactors, which call for novel materials to replace Zircaloy with higher tolerance under extreme conditions.
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