会议专题

DEVELOPMENT OF ADVANCED ODS FERRITIC STEELS FOR FAST REACTOR FUEL CLADDING

  Recent progress of the 9CrODS steel development is presented focusing on their microstructure control to improve sufficient high-temperature strength as well as cladding manufacturing capability.The martensitic 9CrODS steel is primarily candidate cladding materials for the Generation IV fast reactor fuel.They are the attractive composite-like materials consisting of the hard residual ferrite and soft tempered martensite,which are able to be easily controlled by α-γ phase transformation.The residual ferrite containing extremely nanosized oxide particles leads to significantly improved creep rupture strength in 9CrODS cladding.The creep strength stability at extended time of 60,000 h at 700 ℃ is ascribed to the stable nanosized oxide particles.It was also reviewed that 9CrODS steel has well irradiation stability and fuel pin irradiation test was conducted up to 12 at%burnup and 51 dpa at the cladding temperature of 700℃.

ODS Martensite Ferrite Pining force Oxide particle Creep Rupture Strength

S.Ukai N.Oono S.Ohtsuka T.Kaito

Materials Science and Engineering,Faculty of Engineering,Hokkaido University,N13,W8,Sapporo,060-8628 Japan Atomic Energy Agency,4002,Oara,Ibaraki,311-1393,Japan

国际会议

Energy Materials 2014(第一届能源材料国际会议)

西安

英文

43-52

2014-11-04(万方平台首次上网日期,不代表论文的发表时间)