Microstructural development of a heavily neutron-irradiated ODS ferritic steel (MA957) at elevated temperature
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N. Akasaka | Shigeharu Ukai | Shinichiro Yamashita | S. Ohnuki | Soumei Ohnuki | S. Ukai | S. Yamashita | N. Akasaka
[1] A. Kohyama,et al. Microstructural evolution of an oxide dispersion strengthened steel under charged particle irradiation , 1988 .
[2] Shigeharu Ukai,et al. R&D of oxide dispersion strengthened ferritic martensitic steels for FBR , 1998 .
[3] T. Okuda,et al. Development of 9Cr-ODS Martensitic Steel Claddings for Fuel Pins by means of Ferrite to Austenite Phase Transformation , 2002 .
[4] David S. Gelles,et al. Microstructural examination of commercial ferritic alloys at 200 dpa , 1995 .
[5] W. Vandermeulen,et al. Fabrication and mechanical properties of oxide dispersion strengthening ferritic alloy (canning tubes) for fast reactor fuel pins , 1985 .
[6] K. F. Russell,et al. Nanometer scale precipitation in ferritic MA/ODS alloy MA957 , 2004 .
[7] F. Garner,et al. Irradiation creep of various ferritic alloys irradiated at ∼400°C in the PFR and FFTF reactors , 1998 .
[8] Hideharu Nakashima,et al. Characterization of High Temperature Creep Properties in Recrystallized 12Cr-ODS Ferritic Steel Claddings , 2002 .
[9] D. Gelles,et al. Irradiation creep and swelling from 400 to 600 °C of the oxide dispersion strengthened ferritic alloy MA957 , 2004 .
[10] M. Mathon,et al. Assessment of ODS-14%Cr ferritic alloy for high temperature applications , 2004 .