The Tentative Materials Strength Standard of ODS Ferritic Steel Claddings

Kaito, Takeji ; Mizuta, Shunji ; Uwaba, Tomoyuki ; Otsuka, Satoshi   ; Ukai, Shigeharu  

Oxide Dispersion Strengthened (ODS) ferritic steel has excellent swelling resistance and improved high-temperature strength, which are important properties for fast reactor fuel cladding tube. In feasibility study (FS) which is advanced by Japan Nuclear Cycle Development Institute (JNC), ODS ferritic steel is noticed as a prospective candidate material for commercialized fast reactor (FR) fuel cladding tube. JNC has developed a microstructure control procedure to disperse nano-sized oxide particles in equiaxed crystal grain and succeeded in producing high performance ODS ferritic steel tube, which has adequate mechanical properties. For the purpose of getting irradiation data base and evaluating applicability of ODS ferritic steel, fuel pin irradiation test of ODS ferritic steel cladding in FR such as JOYO is in the planning stage.This report describes a summary of the tentative materials strength standard of ODS ferritic steels for designing of FR fuel pin.