Oxide-dispersion-strengthened steel

To finalize this section, I would like to mention that some papers delve into the studies of radiation tolerance of laminated composites with the thickness of layers not increasing tens of nanometers. By varying the thickness of such materials, we can investigate the main mechanisms of influence produced by interphase boundaries on the behavior of radiation defects. The irradiation of multilayered structures with the ions of inert gases first of all with helium allows for the modeling of processes that may arise during the reactor-induced irradiation of oxide dispersion-strengthened steels and alloys. [Pg.553]

Development of oxide dispersion-strengthened steels in Japan... [Pg.361]

Development of other oxide dispersion-strengthened steels... [Pg.383]

Corrosion tests have been performed with supercritical water at temperatures up to 650°C with two ferritic-martensitic steels, four austenitic stainless steels, three ODS (oxide dispersion strengthened) steels, and one Ni-based alloy. The first SCC... [Pg.582]

Y. Chen, K. Sridharan, et al., Oxidation of 9Cr Oxide Dispersion Strengthened Steel Exposed in Supercritical Water, Journal of Nuclear Materials, Vol. 371, 118-128 (2007)... [Pg.596]

G.J. Grant, S. Koduri, and D.R. Herling, Friction Stir Welding of Ma957 Oxide Dispersion Strengthened Ferritic Steel, Friction Stir Welding and Processing III,... [Pg.30]

Monnet, L, Dubuisson, R, Serruis, Y. et al. 2004. Micro structural investigation of the stability under irradiation of oxide dispersion strengthened ferritic steels. J. Nucl. Mater. 335 311-321. [Pg.556]

Studies on Oxide Dispersion Strengthened (OPS) ferritic steel have been started regarding weldability and new grades are developed based on EM 10 ferritic stainless-steel. [Pg.54]

In stainless steels for high-temperature applicahons, RE metals, chiefly yttrium, are used to improve the oxidation resistance. Yttrium is also used in ODS aUoys (Oxide Dispersion Strengthened). Yttrium oxide parhcles with grain size 50-1500 A are distributed in a matrix of some high-aUoy material. The finely dispersed Y Oj particles obstruct the dislocahon movement in the alloy and thus improve the creep properties at high temperature. The ODS ahoy is manufactured by extrusion or by HIP (Heat Isostatic Pressing). [Pg.478]

Kaito, T., Ohtsuka, S., Yano, Y., Tanno, T., Yamashita, S., Ogawa, R., Tanaka, K., 2013. Irradiation Performance of Oxide Dispersion Strengthened (ODS) Ferritic Steel Claddings for Fast Reactor Fuels. FR 13, paper CN-199-252. [Pg.116]

Identify the main classes of stmctural materials for Generation-IV reactors steels oxide dispersion strengthened (ODS) steels refractory alloys ceramics composites. [Pg.278]

Kaito, T., et al., 2007. Progress in the R D project on oxide dispersion strengthened and precipitation hardened ferritic steels for sodium cooled fast breeder reactor fuels. In GLOBAL 2007, September 9—13, 2007, Boise, Idaho, USA. [Pg.304]

Yano, Y., et al, 2011. Effects of neutron irradiation on tensile properties of oxide dispersion strengthened (ODS) steel claddings. Journal of Nuclear Materials 419, 305—309. [Pg.308]

For such systems, metals, oxide dispersion-strengthened (ODS) alloys, ferritic-martensitic steels, and some superaUoys offer potential solutions but some require significant R D in terms of their properties and behavior under component conditions. Such systems may also require the deployment of nonmetallic materials (e.g., high-temperature fibrous insulation, composites, and ceramics) as alternatives to metals for different applications and components. The following sections provide a brief description of the six systems being considered within the GIF technology roadmap. [Pg.6]

Oxide dispersion-strengthened/ ferrite-martensite steels as core materials for Generation IV nuclear reactors... [Pg.357]

M. Inoue, T. Kaito, S. Ohtsuka, Research and development of oxide dispersion strengthened ferritic steels for sodium cooled fast breeder reactor fuels, in V. Ghetta, D. Gorse, D. Maziere, V. Pontikis (Eds.), Materials Issues for Generation IV Systems, 2008, pp. 311-325. [Pg.410]

S. Ukai, T. Kaito, S. Ohtsuka, T. Narita, M. Fujiwara, T. Kobayashi, Production and properties of nano-scale oxide dispersion strengthened (ODS) 9Cr martensitic steel claddings, ISU Int. 43 (12) (2003) 2038-2045. [Pg.410]

T. Yoshitake, Y. Abe, N. Akasaka, S. Ohtsuka, S. Ukai, A. Kimura, Ring-tensile properties of irradiated oxide dispersion strengthened ferritic/martensitic steel claddings, J. Nucl. Mater. 329-333 (2004) 342-346. [Pg.413]

S. Yamashita, Y. Yano, S. Ohtsuka, T. Yoshitake, T. Kaito, S. Koyama, K. Tanaka, Irradiation behavior evaluation of oxide dispersion strengthened ferritic steel cladding tubes irradiated in JOYO, J. Nucl. Mater. 442 (2013) 417—424. [Pg.414]

M.L. Lescoat, J. Ribis, Y. Chen, E.A. Marquis, E. Bordas, P. Trocellier, Y. Serruys, A. Gentils, O. Kaitasov, Y. de Carlan, A. Legris, Radiation-induced Ostwald ripening in oxide dispersion strengthened ferritic steels irradiated at high ion dose, Acta Mater. [Pg.414]

Similar studies have been reported by Ampomrat and Was on ferritic-martensitic alloys (T91, HCM12A, HT-9), Chen et al. on oxide dispersion strengthened 9Cr ferritic steel (9Cr ODS), and by Motta et al., also on 9Cr ODS steel. The findings of these studies are all broadly similar, where measmed, the oxidation follows a parabohc rate law and the oxide layer exhibits a bilayer (or, sometimes, a multilayer) structure comprising a chromirnn-iich spinel inner (barrier) layer and a porous, outer layer of magnetite. The proposed oxidation mechanisms are essentially the same as that articulated by Was et al." ... [Pg.86]

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