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nano-sized oxide particles in ferritic ODS steels has better resistance to neutron
irradiation which acts as a barrier for dislocation and further resisting embrittlement and void swelling when compared with conventional ferritic steels. For heat
resistance, structural applications like fast breeder reactors and thermal power plant
high chromium FSS are widely used. Schroeder and Klueh et al. [1, 2] reported
that for high-temperature applications the BCC (body-centred cubic crystal) FSS
will have good swelling resistance, high tensile/compressive strength, good oxidation resistance, low coefficient of thermal expansion, high thermal conductivity, and
creep resistance. But Kim et al. [3] reported that above 550°C FSS have restriction in creep strength and swilling. To overcome these deficiencies the FSS metal
matrix is strengthened with nano oxide which is homogeneously dispersed which
improves strength and prevents grain boundary slipping both at room and high
temperatures. When compared to ASS, FSS has better mechanical properties and
swelling resistance at high temperatures as reported by Henry et al. [4] ferritic ODS
steel one of the majority hopeful structural materials for advanced nuclear applications, oxide particles which contain the immense number of density. McClintock
et al. [5] reported that ferritic ODS steels confirm admirable high-temperature creep
resistance, promising irradiation resistance and tensile properties due to the presence
of its unique microstructure.
Recent literature reported that the addition of nano-sized, highly dispersed ZrO 2
particles in the ferritic ODS alloy attributed thermal stability by Zener pinning of
grain boundaries. The addition of optimum chromium content of (< 18 wt% Cr >
13 wt%) in the ferritic ODS steel enhances corrosion resistance and tensile strength.
These nano-sized oxides produced by mechanical alloying further strengthened by
solution hardening with the addition of aluminium. With the addition of zirconium
into ODS steel, appropriate to sustain a superior strength and resistance to corrosion.
Finally, the zirconium (Zr) addition into aluminium, Yttrium ODS steels, which leads
to an enhancement in the resistance to the irradiation harm with oxides exhibiting
thermal stability and superior irradiation acceptance reported by Karak et al. [6].
With different weight percentages of chromium Li et al. [7] studied the oxidation
behaviour of ferritic ODS alloys. It was suggested that due to the effects of Y 2 O 3
addition in 12-Cr wt% ferritic ODS alloys have greater high-temperature oxidation
resistance when compared to 9-Cr wt% ferritic ODS steel. It was also mentioned that
the 13-Cr wt% ferritic ODS alloys have a very good oxidation rate at a temperature
level of 1000°C superior to the 21-Cr wt% ferritic ODS alloys, due to development
of a defensive chromium oxide layer.
Macia et al. [8] stated that grain growth for the duration of the sintering process
is one of the key issues for Powder Metallurgy. It is possible to homogeneously
distribute fine dispersoids such as ultrafine Y 2 O 3 , TiO 2, and ZrO 2 oxide particles
to prevent grain growth at high temperature through a mechanical alloying process.
The nano oxide particles especially Yttrium with titanium (Ti) added ODS alloys to
refine the oxide particle size at their forming temperature of 1000–1150 °C. These
non-stoichiometric enriched complex oxides (Y–Ti–O) found additional efficiency
in attractive creep resistance and irradiation resistance due to their smaller sizes.
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