Concepedia

Fuel Pin Irradiation Test at up to 5 at% Burnup in BOR-60 for Oxide-Dispersion-Strengthened Ferritic Steel Claddings

Takeji Kaito, Shigeharu Ukai, A.V. Povstyanko

Journal of Nuclear Science and Technology · 2009 · 15 citations · 7 references

DOI

Concepts

Abstract

Click to increase image sizeClick to decrease image sizeKEYWORDS: cladding materialfast reactor materialODSMOX fuelfuel pinirradiationFCCIO/M ratioBOR-60

References

7

Development of 9Cr-ODS Martensitic Steel Claddings for Fuel Pins by means of Ferrite to Austenite Phase Transformation

Shigeharu Ukai, S Mizuta, Masayuki Fujiwara et al. · Journal of Nuclear Science and Technology · 2002 · 198 citations

, , +17

Characterization of High Temperature Creep Properties in Recrystallized 12Cr-ODS Ferritic Steel Claddings

Shigeharu Ukai, T. Okuda, Masayuki Fujiwara et al. · Journal of Nuclear Science and Technology · 2002 · 191 citations

, , +17

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

Shigeharu Ukai, Takeji Kaito, Satoshi Ohtsuka et al. · ISIJ International · 2003 · 98 citations · Full text

, , +17

Pressurized resistance welding technology development in 9Cr-ODS martensitic steels

Masako Seki, Kazuhito Hirako, Shusaku KONO et al. · Journal of Nuclear Materials · 2004 · 46 citations

, , +14

Oxide Dispersion Strengthened (ODS) Fuel Pins Fabrication for BOR-60 Irradiation Test

Shigeharu Ukai, Takeji Kaito, Masayuki Seki et al. · Journal of Nuclear Science and Technology · 2005 · 36 citations

, , +17