Induced nuclear reactions: processes – systems – and elements – Fuel component structure – Encased with nonfuel component
Patent
1992-12-30
1994-01-11
Walsh, Donald P.
Induced nuclear reactions: processes, systems, and elements
Fuel component structure
Encased with nonfuel component
376414, 376417, 427 6, 427239, G21C 300
Patent
active
052788822
ABSTRACT:
A stabilized alpha metal matrix provides an improved ductility, creep strength, and corrosion resistance against irradiation in a zirconium alloy containing on a weight percentage basis tin in a range of 0.4 to 1.0 percent and typically 0.5; iron in a range of 0.3 to 0.6 percent, and typically 0.46 percent; chromium in a range of 0.2 to 0.4 percent, and typically 0.23 percent; silicon in a range of 50 to 200 ppm, and typically 100 ppm; and oxygen in a range 1200 to 2500 ppm, typically 1800 to 2200 ppm. The high oxygen level assists in reducing hydrogen uptake of the alloy compared to Zircaloy-4, for example.
REFERENCES:
patent: 4648912 (1987-03-01), Sabol et al.
patent: 4649023 (1987-03-01), Sabol et al.
patent: 4664831 (1987-05-01), Hibst 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.
Isobe, T. and Matsuo, Y., "Development of High Corrosion Resistant Zirconium-base Alloys", Zirconium in the Nuclear Industry: Ninth International Symposiu, ASTM STP 1132, C. M. Eucken and A. M. Garde, Eds. American Society for Testing Materials, Philadelphia, 1991, pp. 346-367.
Burton , B., Donaldson, A. T., and Reynolds, G. L., "Interaction of Oxidation and Creep in Zircaloy-2", ASTM STP 681, 1979, pp. 561-585.
Adamson, R. B., and Bell, W. L., "Effects of Neutron Irradiation and Oxygen Content on the Microstructure and Mechanical Properties of Zircaloy", Microstructural and Mechanical Behavior of Materials, vol. 1, G. Haicheng and H. Jiawen, Editors; Engineering Materials Advisory Services, UK 1985 pp. 237-246.
Eucken C. M., Finden, P. T., Trapp-Pritsching, S. and Weidinger, H. G., "Influence of Chemical Composition on Uniform Corrosion of Zicronium Base Alloy in Autoclave Tests" Zicronium in the Nuclear Indutry 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).
Garde Anand M.
Pati Satya R.
Combustion Engineering Inc.
Kananen Ronald P.
Mulholland John H.
Voss Frederick H.
Walsh Donald P.
LandOfFree
Zirconium alloy with superior corrosion resistance does not yet have a rating. At this time, there are no reviews or comments for this patent.
If you have personal experience with Zirconium alloy with superior corrosion resistance, we encourage you to share that experience with our LandOfFree.com community. Your opinion is very important and Zirconium alloy with superior corrosion resistance will most certainly appreciate the feedback.
Profile ID: LFUS-PAI-O-1636746