Microstructural development under irradiation in European ODS ferritic/martensitic steels

The oxide phases in oxide dispersion strengthened PM2000 steel have been investigated by transmission electron microscopes. Two nano-sized yttrium aluminum oxide phases, YAlO3 having a distorted orthorhombic-simple structure with approximate lattice parameters of a/b/c = 5.4197/5.8520/7.6413 Å and Y3Al5O12 having a tetragonal-simple crystal structure, have been identified in the steel. Two aluminum iron oxide phases and one aluminum titanium oxide phase, which are not known to have been identified previously in steels, have been found in the PM2000 steel. They have been determined to be aluminum iron oxide, Al2Fe2O6 having an orthorhombic crystal structure with the lattice parameters a/b/c = 7.235/5.926/ 7.502 Å, and aluminum iron oxide, Al3FeO6 having a body-centered cubic crystal structure with an average lattice parameter of 3.047 Å, as well as aluminum titanium oxide, Al3Ti5O2 having a face-centered cubic crystal structure with an average lattice parameter of 6.923 Å. The PM2000 steel contains a small amount of Al2Fe2O6, Al3FeO6, Al3Ti5O2 and Al2O3 phases with a large size and block/ or spherical morphology.

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“…1,2) ODS steels are being developed and investigated for nuclear fission and fusion applications in Japan, Europe, and the United States.…”

Section: Introductionmentioning

confidence: 99%

Identification of Oxide Phases in Oxide Dispersion Strengthened PM2000 Steel

et al. 2013

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“…In the case of a submicrometre grained ODS steel, the nanoparticle/ matrix interfaces and the large volume fraction of grain boundaries provide a large amount of sinks for irradiation defects, reducing the deleterious impact of radiation damage. 7,8 In addition, the nanoparticle/matrix interfaces also appear to compete with the grain boundaries as He and H (produced by neutron transmutation) trapping sites. 9,10 Thus, the homogeneous dispersion of nanoparticles should act as an effective inhibitor for the formation of gas bubbles at the grain boundaries, which is responsible for the premature failure of neutron irradiated steels.…”

Section: Introductionmentioning

confidence: 99%

Analytical characterisation of oxide dispersion strengthened steels for fusion reactors

Castro

Lozano-Pérez

Marquis

et al. 2011

Materials Science and Technology

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Reduced activation ferritic/martensitic and ferritic steels strengthened by a dispersion of oxide nanoparticles have been considered viable structural materials for fusion applications above 550uC. However, the microstructural stability and mechanical behaviour of these steels subjected to the aggressive operating conditions of these reactors are not well known. An accelerated development of these materials is crucial if they are going to be used in future power reactors. Then, it is indispensable to understand their atomic scale evolution under high temperature and irradiation conditions. The present paper reviews how the combination of transmission electron microscopy and atom probe tomography has been successfully applied for the characterisation of these steels at the near atomic scale, to reveal the nanoparticle structure, grain boundary chemistry and void distribution.

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“…Both ODS and EUROFER 97 steels were prepared by powder metallurgy methods at the Centre of Research in Plasma Physics (CRPP, Switzerland) [5] and at the CEA Grenoble, France [6], respectively.…”

Section: Methodsmentioning

confidence: 99%