Zirconium alloy with improved post-irradiation properties

Details Zirconium alloy with improved post-irradiation properties Zirconium alloy with improved post-irradiation properties

1992-12-24

1993-10-19

Roy, Upendra

Alloys or metallic compositions

Zirconium or hafnium base

148672, C22C 1600

Patent

active

052543080

ABSTRACT:
A stabilized alpha metal matrix provides an improved ductility, creep strength, and corrosion resistance against irradiation in a zirconium alloy containing tin in a range of 0.45 to 0.75 wt. %, and typically 0.6 wt. %; iron in a range of 0.4 to 0.53 wt. %, and typically 0.45 percent; chromium in a range of 0.2 to 0.3 wt. %, and typically 0.25 percent; niobium in a range of 0.3 to 0.5 wt. %, and typically 0.45 wt. %; nickel in a range of 0.012 to 0.03 wt. %, and typically 0.02 wt. %; silicon in a range of 50 to 200 ppm, and typically 100 ppm; and oxygen in a range 1,000 to 2,000 ppm, and typically 1,600 ppm, with the balance zirconium. The addition of iron and niobium improves mechanical properties of the alloy with its lower level of tin, while corrosion resistance is addressed by having an iron level of 0.45 wt. % and an iron/chromium ratio on the order of 1.5. The addition of niobium also counters the effect of higher iron on the hydrogen absorption characteristics of the alloy. The addition of nickel, silicon, carbon, and oxygen as alloying elements provide desired corrosion resistance and strength.

REFERENCES:
patent: 4648912 (1987-03-01), Sabol et al.
patent: 4649023 (1987-03-01), Sabol et al.
patent: 4675153 (1987-06-01), Boyle et al.
patent: 4879093 (1989-11-01), Garde
patent: 4938920 (1990-07-01), Garzarolli et al.
patent: 4963323 (1990-10-01), Matsuo et al.
patent: 4992240 (1991-02-01), Komatsu et al.
patent: 5023048 (1991-06-01), Mardon et al.
patent: 5112573 (1992-05-01), Foster et al.
patent: 5125985 (1992-06-01), Foster et al.
Eucken C. M., Finden, P. T., Trapp-Pritsching, S. and Weidinger, H. G., "Influence of Chemical Composition on Uniform Corrosion of Zirconium Base Alloy in Autoclave Tests" Zirconium in the Nuclear Industry Eighth International Symposium, ASTM STP 1023, L. F. P., Van Swam and C. M. Eucken, Eds.; American Society for Testing and Materials, Philadelphia, 1989, pp. 113-127.
McInteer, W. A., Baty, D. L. and Stein, K. O., "The Influence of Tin Content on the Thermal Creep of Zircaloy-4", Zirconium in the Nuclear Industry, Eighth International Symposium, ASTM STP 1023, L. F. P. Van Swam and C. M. Eucken, Eds.; American Society for Testing and Materials, Philadelphia, 1989 pp. 621-640.
Scott, D. B., "Notes on the Corrosion Behavior of Zircaloy-2 with Various Levels of Iron Content," Zirconium Highlights, WAPD-ZH-24, p. 11, (1960).
Isobe, T. and Matsuo, Y., "Development of High Corrosion Resistant Zirconium-base Alloys", Zirconium in the Nuclear Industry: Ninth International Symposium, ASTM STP 1132, C. M. Eucken and A. M. Garde, Eds. American Society for Testing Materials, Philadelphia, 1991, pp. 346-367.

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