Fabrication and Mechanical Properties of Oxide Dispersion Strengthening Ferritic Alloy Canning Tubes for Fast Reactor Fuel Pins

Production and Properties of Nano-scale Oxide Dispersion Strengthened (ODS) 9Cr Martensitic Steel Claddings

“…Shigeharu UKAI, Takeji KAITO, Satoshi OHTSUKA, Tsuyoshi NARITA, Masayuki FUJIWARA 1) and Toshimi KOBAYASHI 2) O-arai Engineering Center, Japan Nuclear Cycle Development Institute, Narita, O-arai, Ibaraki 311-1393 Japan. 1) Kobelco Research Inc., Kobe, Hyogo 651-2271 Japan.…”

“…1) The oxide dispersion strengthened (ODS) martensitic steel is expected to be a good candidate of the materials having a potential of superior high temperatures strength over 923 K. Since FMS is well known to have far superior radiation resistance compared with austenitic steels, the ODS martensitic steel is expected to be a promising cladding material in the long-life core of fast reactor fuel pins [2][3][4][5][6] as well as a low activated fusion reactor materials.…”

Effect of Ti and W on the Mechanical Properties and Microstructure of 12% Cr Base Mechanical-alloyed Nano-sized ODS Ferritic Alloys

“…It has been reported by a number of researchers [1][2][3][4][5][6][7][8][9] that MA ODS alloys possess excellent creep strength at high temperatures and high resistance to swelling in radioactive radiation. Oxide dispersion strengthened (ODS) ferritic alloys produced by mechanical alloying (MA) have been found to be effective for increasing high-temperature strength.…”

Elevated-Temperature Ferritic and Martensitic Steels and Their Application to Future Nuclear Reactors

“…Two early compositions studied extensively were: Fe-13Cr-1.5Mo-2.9Ti-1.8Ti 2 O 3 (DT2906) and Fe-13Cr-1.5Mo-2.2Ti-0.9Ti 2 O 3 -0.5Y 2 O 3 (DT2203Y05). 126,128 Elevated-temperature strength is provided by a dispersion of fine titania and yttria particles and by χ-phase (70% Fe, 15% Cr, 7% Ti, 6% Mo) that forms at grain boundaries.…”