Effect of the Initial Powder and Treatment on the Structure of Oxide Dispersion-Strengthened Steel

Atomic Energy ◽  
2014 ◽  
Vol 116 (1) ◽  
pp. 42-47 ◽  
Author(s):  
I. I. Chernov ◽  
M. S. Stal’tsov ◽  
B. A. Kalin ◽  
I. A. Bogachev ◽  
M. A. Burlakova ◽  
...  
2015 ◽  
Vol 89 ◽  
pp. 141-152 ◽  
Author(s):  
Xiaodong Mao ◽  
Kyu Hwan Oh ◽  
Suk Hoon Kang ◽  
Tae Kyu Kim ◽  
Jinsung Jang

2010 ◽  
Vol 1264 ◽  
Author(s):  
Olena Kalokhtina ◽  
Bertrand Radiguet ◽  
Yann de Carlan ◽  
Philippe Pareige

AbstractA high chromium ferritic Oxide Dispersion Strengthened steel was produced by mechanical alloying of Fe-18Cr-1W-0.3Ti-0.3Ni-0.15Si and 0.5% Y2O3 (wt.%) powders in industrial attritor, followed by hot extrusion at 1100°C. The material was characterized by Atom Probe Tomography on each step of manufacturing process: as-milled powder and in final hot extruded state. In addition, to get information on clustering kinetics the powder was also characterized after annealing at 850°C during 1 hour. Atom Probe Tomography revealed that the oxide dispersion strengthened steel Fe-18Cr contains nanometer scale yttrium- and oxygen-enriched nanoclusters in as-milled state. Their evolution is shown after subsequent annealing and hot extrusion. More well defined nanophases also enriched in Ti are observed. A mechanism of their formation is proposed. Mechanical alloying results in supersaturated solid solution with presence of small Y- and O-enriched clusters. Subsequent annealing stimulates incorporation of Ti to the nucleii that were previously formed during mechanical alloying.


2011 ◽  
Vol 1298 ◽  
Author(s):  
A. Richter ◽  
C.-L. Chen ◽  
A. Mücklich ◽  
R. Kögler

ABSTRACTAn oxide dispersion strengthened steel is produced which contains Y-Al-Ti-O nanoparticles with an average diameter of 21 nm. HRTEM analysis shows that the chemical composition of the Y2O3 oxide is modified with perovskite YAlO3 (YAP), Y2Al5O12 garnet (YAG) and Y4Al2O9 monoclinic (YAM) particles. Irradiation of these alloys was performed with a dual ion beam system operating simultaneously with 2.5 MeV Fe+ to 31 dpa and 350 keV He+ to 18 appm/dpa. Ion bombardment causes atomic displacements resulting in vacancy and self-interstitial lattice defects and dislocation loops. TRIM calculations for ODS steel indicate a clear spacial separation between vacancies and self-interstitials at which the vacancy distribution is close to the surface and the interstitials are deposited at a deeper position. The helium atoms mainly accumulate in the vacancies. Fine He cavities with diameters of a few nanometers were identified in HRTEM images. Additionally to structural changes, irradiation generated defects also affect the mechanical properties of the ODS steel. These were investigated by nanoindentation, which is a suitable measuring method as the irradiation damage is created within a thin surface layer. A clear hardness increase in the irradiated depth region was observed, which reaches a maximum close to the surface. This indicates the He condensation in the vacancy dominated region predicted by the simulations.


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