Development of Advanced Steels for Irradiation Environment

点击翻译按钮获取中文摘要

1. When 316 stainless steel was electron-irradiated, stacking fault dislocation loops were nucleated, and then finally stacking fault tetrahedra of vacancy type (SFT) were nucleated inside the loops. These SFTs acted as void nucleation sites under electron/He dual irradiation.2. Fe-(15-16)% Cr-16% Mn-O.2% C-O.2% N steels have yield stress of 400 MPa and the elongation of 60% at room temperature. These high Mn steels showed excellent irradiation-resistance under irradiation.3. When Fe-Cr-Mn(W,V) steels with W and V were irradiated, no segregation was recognized, and then it was suggested that by adding W, and V segregation is retarded.4. The same Fe-Cr-Mn containing W and V showed higher resistance for irradiation at625K but at higher temperature a lot of small voids were nucleated.5. In Fe-Cr-Mn steels the segregation at grain boundary was larger than the steel with W and V.6.lt was clarified for Fe-(13-16) Cr-(6.5-24.5) Mn-(0.02-0.2)C-0.2 N steels that (a) by contorolling the composition of Cr, C,N single phase of austenite can be obtained even for lower Mn concentration steels, (b)Fe-(15-16)wt% Cr-15.5wt% Mn-(O.02-O.2)wt% C-0.2wt% N steels have excellent mechanical properties, and (c) voids formation were perfectly retarded for Fe-l6wt% Cr-15.5wt% Mn-O.2wt% C-O.2wt% N steel under irradiation at 473-673K.