FIELD: nuclear power engineering. SUBSTANCE: zirconium-alloy tubular can that also includes 0.18-0.25% of iron, 0.07-0.13% of chromium, 0.35-1.7 mass percent of tin, 900-2800 ppm of oxygen, 80 to 200 ppm of carbon, 50 to 120 ppm of silicon with mass proportion of iron and chromium in alloy being 1.6 to 3 is subjected to post-rolling heat treatment including several annealing procedures in inert atmosphere where ΣA is higher than 1,5•10-17. ΣA means here total complex of annealing procedures, products of terms t, h, and Q/RT exponential function, where T is temperature, K. EFFECT: improved corrosion resistance in water at high temperature with adequate stability of thermal yield and on-load corrosion resistance.
Authors
Dates
2000-02-20—Published
1994-12-20—Filed