56 research outputs found
Influence of Y2O3 and Fe2Y additions on the formation of nano-scale oxide particles and the mechanical properties of an ODS RAF steel
The main goal of this work was to manufacture an oxide dispersion strengthened (ODS) reduced activation ferritic steel from a pre-alloyed, gas atomised Fe-14Cr-2W-0.2Ti (in wt.%) powder mechanically alloyed with either 0.3%Y2O(3) or 0.5%Fe2Y particles and consolidated by hot isostatic pressing, and to investigate its microstructure, microhardness and Charpy impact properties
Microstructure and mechanical properties of an ODS RAF steel fabricated by hot extrusion or hot isostatic pressing
Ingots of an oxide dispersion strengthened reduced activation ferritic steel with the Fe-14Cr-2W-0.3Ti-0.3Y(2)O(3) chemical composition (in wt.%) were synthesized by mechanical alloying of elemental powders with 0.3 wt.% Y2O3 particles in a planetary ball mill, in a hydrogen atmosphere. and compacted by either hot extrusion or hot isostatic pressing. The microstructures of the obtained materials were characterized by means of light microscopy, transmission electron microscopy and chemical analyses. The mechanical properties were evaluated by means of Vickers microhardness measurements and tensile tests. It was found that the microstructure of both materials is composed of ferritic grains having a submicron size and containing nanometric Y-Ti-O oxide particles with a mean size of about 10 nm, uniformly distributed in the matrix. The oxide particles in the hot extruded steel were identified as YTiO3 phase. In larger (>10 nm) oxide particles Cr was found next to Ti, Y and O. The steel produced by hot extrusion exhibits much higher tensile strength and hardness at low to moderate temperatures, as compared to the steel fabricated by hot isostatic pressing, which was mainly attributed to smaller pores but also to more severe work hardening in the case of the hot extruded steel. (C) 2011 Elsevier B.V. All rights reserved
From materials development to their test in IFMIF: an overview
R&D activities on fusion reactor materials in Switzerland focus on (1) the development of advanced metallic materials for structural applications in plasma-facing (first wall, divertor) and breeding blanket components of the future fusion power reactors, in particular oxide dispersion strengthened reduced activation ferritic steels and tungsten-base materials, (2) the modelling of radiation damage and radiation effects and (3) small specimen test technology for the future International Fusion Materials Irradiation Facility. The main objectives, examples of recent results and future activities are described in the case of these three R&D areas
Review on the EFDA work programme on nano-structured ODS RAF steels
This proceeding is: The 14th International Conference on Fusion Reactor Materials (ICFRM-14) was held at the Sapporo Convention Center in Sapporo, Japan from 7 to 12 September 2009.The 2008─2009 work programme of the European research project on nano-structured oxide dispersion strengthened (ODS) reduced activation ferritic (RAF) steels is being organized along the four following programmatic lines: (1) improve the present generation of nano-structured ODS RAF steels; (2) start the industrial fabrication of the present generation of nano-structured ODS RAF steels; (3) develop an optimised generation of nano-structured and nano-grained ODS RAF steels; (4) investigate the stability of present and optimised generation of nano-structured ODS RAF steels under creep and irradiation. This paper presents the main objectives of current R&D activities being performed within the European research project on nano-structured ODS RAF steels, the main obtained results and the main future activities in the case of the four programmatic lines mentioned just above.This work, supported by the European Communities, was carried out within the framework of the European Fusion Development Agreement.Publicad
Incorporation of Y2O3 Particles into 410L Stainless Steel by a Powder Metallurgy Route
Addition of yttria to steels has been proposed for the fabrication of oxide-dispersion-strengthened materials for nuclear power applications. We have investigated materials prepared from 12 Cr martensitic stainless steel, AISI 410L, produced by powder metallurgy. Materials were produced with and without yttria addition, and two different sizes of yttria were used, 0.9 µm and 50 nm. Tensile and mini-creep tests were performed to determine mechanical properties. Optical microscopy, SEM, TEM, and EDX analysis were used to investigate the microstructures and deformation mechanisms and to obtain information about non-metallic inclusion particles. SiO2, MnS, and Y2Si2O7 inclusion particles were observed. An SiO2 and Y2O3 interaction was seen to have occurred during the ball milling, which impaired the final mechanical properties. Small-angle neutron scattering experiments showed that the matrix chemistry prevented effective dissolution of the yttria. © The Author(s) 201
Microstructural Changes of Ods Ferritic Steel Powders During Mechanical Alloying
The ODS ferritic steel powder with chemical composition of Fe-14Cr-2W-0.3Ti-0.3Y2O3 was mechanically alloyed (MA) either from elemental or pre-alloyed powders in a planetary ball mill. Different milling parameters have been used to investigate their influence on the morphology and microstructure of the ODS ferritic steel powder. The time of MA was optimized by studying the structural evolution of the powder by means of X-ray diffractometry and TEM. In the case of elemental powder very small, about 10 žm in diameter, spherical particles with a large surface area have been obtained. Flakey-like particles with an average size of about 45 žm were obtained in the case of the pre-alloyed powder. The lattice strain calculated from XRD spectra of the elemental and pre-alloyed powders exhibits a value of about 0.51 % and 0.67, respectively. The pre-alloyed powder after consolidation process showed the highest density and microhardness value
Comparison of corrosion resistance in physiological saline solution of two austenitic stainless steels – 316LV and REX734
In this work two austenitic stainless steels, REX734 and 316LV were tested in terms of their microstructure and corrosion properties.
The REX734 is a newer generation stainless steel, with modified chemical composition, in comparison to the 316LV grade. Potentiodynamic
study of corrosion resistance was conducted in physiological saline solution (0.9% NaCl solution). In spite of the similarities
of microstructure, grain size and phase structure in both materials, the corrosion tests revealed that the REX734, with lower nickel
and higher nitrogen content, had better corrosion resistance than 316LV. Repassivation potential in the REX734 was almost six times
higher than for the 316LV steel. Superior corrosion resistance of the REX734 steel was also confirmed by surface observations of both materials,
since bigger and more densely distributed pits were detected in 316LV alloy
Corrosion Resistance of Mechanically Alloyed 14% Cr ODS Ferritic Steel
New classes of singular fractional continuous-time and discrete-time linear systems are introduced. Electrical circuits are example of singular fractional continuous-time systems. Using the Caputo definition of the fractional derivative, the Weierstrass regular pencil decomposition and Laplace transformation the solution to the state equation of singular fractional linear systems is derived. It is shown that every electrical circuit is a singular fractional systems if it contains at least one mesh consisting of branches with only ideal supercondensators and voltage sources or at least one node with branches with supercoils. Using the Weierstrass regular pencil decomposition the solution to the state equation of singular fractional discrete-time linear systems is derived. The considerations are illustrated by numerical examples
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