journal article·2009-03

Development of oxides dispersion strengthened steels for high temperature nuclear reactor applications

K. Verhiest, A. Almazouzi, N. De Wispelaere, R. Petrov, S. Claessens

Journal of Nuclear Materials· Volume 385· Issue 2
Publisher page

Abstract

Abstract By introducing a dispersion of nanosized yttrium oxides particles into a steel matrix, the upper temperature limit in mechanical creep strength can be enhanced in temperature by 100 K at least. Production routes for the production of a new class of oxides dispersion strengthened (ODS) steels are investigated within this work. Preliminary results obtained when doping pure iron matrix phase with two types of yttrium oxides (Y2O3) nanoparticles (commercial as well as laboratory fabricated nanopowder) are presented. The twofold purpose of this work is firstly to obtain a comparative analysis between the commercial and the laboratory fabricated Y2O3 nanopowder used to produce the doped iron, and secondly to demonstrate the feasibility of new production route by observing the nanostructure of the first test batches with pure iron. Observations are carried out with transmission electron microscopy (TEM) to determine the size distribution of the particles in the powder, while glow discharge optical emission spectroscopy (GDOES) and high resolution-scanning electron microscopy (HR-SEM) are used to analyze the chemical composition and the homogeneity of the produced doped iron. It is demonstrated, that even with small size particles nanopowder fabricated in the laboratory, the distribution is fairly homogeneous compared to the one obtained with a relatively large particles commercial nanopowder, confirming the feasibility of the new production route.
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Research context

OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Advanced materials and composites

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (12)

Show source-provided references
1. Lindau · J.Nucl. Mater. · 2002 · 307–311 · 76910.1016/S0022-3115(02)01045-0 ↗
2. Oksiuta · J. Nucl. Mater. · 2008 · 374 · 17810.1016/j.jnucmat.2007.08.004 ↗
3. Alamo · J. Nucl. Mater. · 2007 · 367–370 · 5410.1016/j.jnucmat.2007.03.166 ↗
4. Degueldre · Comp. Mater. Sci. · 2005 · 33 · 310.1016/j.commatsci.2004.12.019 ↗
5. Ukai · J. Nucl. Sci. Technol. · 1997 · 34 · 25610.1080/18811248.1997.9733658 ↗
6. Ukai · J. Nucl. Sci. Technol. · 1999 · 36 · 71010.1080/18811248.1999.9726259 ↗
7. Klueh · J. Nucl. Mater. · 2005 · 341 · 10310.1016/j.jnucmat.2005.01.017 ↗
8. Kim · J. Nucl. Mater. · 2000 · 280 · 26410.1016/S0022-3115(00)00066-0 ↗
9. Capdevilla · Advanced Engineering materials · 2001 · 3 · 910.1002/1527-2648(200109)3:9<647::AID-ADEM647>3.0.CO;2-4 ↗
10. Sikka · Mater. Sci. Eng. A · 1998 · 258 · 22910.1016/S0921-5093(98)00938-1 ↗
11. Igarashi · Appl. Phys. Lett. · 2000 · 76 · 154910.1063/1.126092 ↗
12. Shea · J. Am. Ceram. Soc. · 1996 · 79 · 325710.1111/j.1151-2916.1996.tb08103.x ↗