摘要:
A corrosion resistant zirconium alloy for use as a nuclear reactor cladding material. This alloy consists essentially of, on a weight % basis 0.02-1.7 % Sn, 0.19-0.6% Fe, 0.07-0.4% Cr, 0.01-0.2% Ta, and optionally 0.05 up to less than 0.5% Nb, the balance being Zr and incidental impurities, provided that the content of the nitrogen in the form of incidental impurities is no more than 60 ppm.
摘要:
A corrosion resistant zirconium alloy for use as a nuclear reactor cladding material. This alloy consists essentially of, on a weight % basis 0.02-1.15% Sn, 0.19-0.6% Fe, 0.07-0.4% Cr, and optionally 0.05 to not more than 0.5% Nb, the balance being Zr and incidental impurities, provided that the content of the nitrogen in the form of incidental impurities is no more than 60 ppm.