| 摘要 |
PURPOSE:To obtain a material in which radiation induced segregation in a neutron irradiation environment is prevented and deterioration in corrosion resistance and embrittlement are suppressed by adding specified amounts of one or more kinds among Ti, Zr, Hf, V, Nb and Ta to an austenitic stainless steel and limiting the content of C and N to specified value or below. CONSTITUTION:An austenitic stainless steel contg., by weight, 15 to 18% Cr, 8 to 15% Ni or, in addition to the above, <=3% Mo and contg. <=1% Si and <=2% Mn is mixed with one or more kinds among >0.4 to 0.6% Ti, >0.2 to 1.14% Zr >0.2 to 2.24% Hf, >0.2 to 0.64% V, >1.0 to 1.17% Nb and >1.0 to 27% Ta, in which the content of C is limited to 0.001 to 0.03% and that of N to 0.001 to 0.l% and the balace Fe with inevitable impurities.
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