Oxide dispersion-strengthened ferritic steels

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,... 

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. 

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. 

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. 

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. 

Y. Chen, K. Sridharan, T. R. Allen, S. Ukai, Microstructural examination of oxide layers formed on an oxide dispersion strengthened ferritic steel exposed to supercritical wateT, Journal of Nuclear Materials 359 (2006) 50-58. 

Y. Chen, K. Sridharan, et al., Microstructural Examination of Oxide Layers Formed on an Oxide Dispersion Strengthened Ferritic Steel Exposed to Supercritical Water, Journal of... 

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

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. 

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. 

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. 

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. 

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. 

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." ... 

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... 

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