Oxide dispersion strengthened (ODS) ferritic steels is eligible for fuel pin cladding tubes to endure heavy displacement damages to 250 dpa at high temperatures up to 973 K in commercialized sodium cooled fast breeder reactor cores. Japan Atomic Energy Agency has been developing ODS steels since 1987. For ODS steels, powder metallurgy process including mechanical alloying and hot consolidation produces highly stable and fine oxide dispersoids in matrix, and provides excellent dispersion hardening. Although cold rolling process in tube manufacturing tends to cause anisotropic grain growth, alpha to gamma phase transformation for the 9Cr-ODS steel and recrystallization for the 12Cr-ODS steel can modify grain morphology and improve creep rupture strength under internal pressure. Mechanical properties of the tubes have been extensively tested in air and stagnant sodium environments to establish Material Strength Standard for fuel pin mechanical design. Also, hundreds of specimens have been irradiated in the experimental fast reactor JOYO to investtigate irradiation effect on dimensional stability and mechanical properties. Pressurized resistance welding technology has been applied to join a tube and end plugs. Both 9Cr- and 12Cr-ODS steel tubes were assembled into fuel pins, and have been irradiated since 2003 under the collaborative program in the BOR-60 in Russia.
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References
Bottcher, J., Ukai, S., and Inoue, M., 2002, ODS steel clad MOX fuel-pin fabrication and irradiation performance in EBR-II, Nucl. Technol. 138(3): 238-245.
Kaito, T., Ukai, S., Ohtsuka, S., and Narita, T., 2005, Paper No.169, GLOBAL2005, October 9-13, 2005, Tsukuba, Japan.
Kaito, T., Ohtsuka, S., and Inoue, M., 2007, Paper No.005-175716, GLOBAL2007, September 9-13, 2007, Idaho, USA.
Narita, T., Ukai, S., Kaito, T., Ohtsuka, S., and Kobayashi, T., 2004, Development of twostep softening heat treatment for manufacturing 12Cr-ODS ferritic steel tubes, J. Nucl. Sci. Technol. 41(10):1008-1012.
Narita, T., Ukai, S., Kaito, T., Ohtsuka, S., and Fujiwara, M., 2005, Development of manufacturing process of PNC-FMS wrapper tube with SUS316 short joint, J. Nucl. Sci. Technol. 42(9):825-832.
Ohtsuka S., Ukai S., Fujiwara, M., Kaito, T., and Narita, T., 2004, Improvement of 9Cr-ODS martensitic steel properties by controlling excess oxygen and titanium contents, J. Nucl. Mater. 329-333(1):372-376.
Ohtsuka, S., Ukai, S., Sakasegawa, H., Fujiwara, M., Kaito, T., and Narita, T., 2005, Improvement of creep strength of 9Cr-ODS martensitic steel by controlling excess oxygen and titanium concentrations, Mater. Trans. 46(3):487-492.
Ohtsuka, S., Ukai, S., Fujiwara, M., Kaito, T., and Narita, T., 2005, Nano-structure control in ODS martensitic steel by means of selecting titanium and oxygen contents, J. Phys. Chem. Solids. 66(2-4):571-575.
Ohtsuka, S., Ukai, S., Sakasegawa, H., Fujiwara, M., Kaito, T., and Narita, T., 2007, Nanomesoscopic structural characterization of 9Cr-ODS martensitic steel for improving creep strength, J. Nucl. Mater. 367-370(1):160-165.
Seki, M., Hirako, K., Kono, S., Kihara, Y., Kaito, T., and Ukai, S., 2004, Pressurized resistance welding technology development in 9Cr-ODS martensitic steels, J. Nucl. Mater. 329-333(2):1534-1538.
Ukai, S., Mizuta, S., Fujiwara, M., Okuda, T., and Kobayashi, T., 2002, Development of 9CR-ODS martensitic steel claddings for fuel pin by means of ferrite to austenite phase transformation, J. Nucl. Sci. Technol. 39(7):778-788.
Ukai, S., Hatakeyama, H., Mizuta, S., Fujiwara, M., and Okuda, T., 2002, Consolidation process study of 9Cr-ODS martensitic steels, J. Nucl. Mater. 307-311(1):758-762.
Ukai, S., Kaito, T., Ohtsuka, S., Narita, T., Fujiwara, M., and Kobayashi, T., 2003, ISIJ International 43(12):2038-2045.
Ukai, S., Kaito, T., Seki, M., Mayorshin, A. A., and Shishalov, O. V., 2005, Oxide dispersion strengthened (ODS) fuel pin fabrication for BOR-60 irradiation test, J. Nucl. Sci. Technol. 42(1):109-122.
Ukai, S., Kaito, T., Ohtsuka, S., Narita, T., and Sakasegawa, H., 2006, ANS Annual Meeting, June 4-8, Reno, USA, Trans. Am. Nucl. Soc. 94:786-787.
Yamashita, S., Akasaka, N., and Ohnuki, S., 2004, Nano-oxide particle stability of 9-12Cr grain morphology modified ODS steels under neutron irradiation, J. Nucl. Mater. 329-333 (1):377-381.
Yoshitake, T., Abe, Y., Akasaka, N., Ohtsuka, S., Ukai, S., and Kimura, A., 2004, Ringtensile properties of irradiated oxide dispersion strengthened ferritic/martensitic steel claddings, J. Nucl. Mater 329-333(1):342-346.
Yoshida, E., and Kato, S., 2004, Sodium compatibility of ODS steel at elevated temperature, J. Nucl. Mater. 329-333(2): 1393-1397.
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Inoue, M., Kaito, T., Ohtsuka, S. (2008). Research and Development of Oxide Dispersion Strengthened Ferritic Steels for Sodium Cooled Fast Breeder Reactor Fuels. In: Ghetta, V., Gorse, D., Mazière, D., Pontikis, V. (eds) Materials Issues for Generation IV Systems. NATO Science for Peace and Security Series B: Physics and Biophysics. Springer, Dordrecht. https://doi.org/10.1007/978-1-4020-8422-5_16
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