Zirconium alloy heat treatment process and product

Metal treatment – Process of modifying or maintaining internal physical... – Chemical-heat removing or burning of metal

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148 115F, 148 32, C21D 100

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active

042382513

ABSTRACT:
Zirconium-base alloy channels and fuel cladding tubes having unique resistance to accelerated pustular corrosion in the boiling water reactor environment are produced by a heat treatment causing segregation of intermetallic particulate precipitate phase in two dimensional arrays preferably located along grain boundaries and subgrain boundaries throughout the alloy body.

REFERENCES:
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patent: 3287111 (1966-11-01), Klepfo
patent: 3865635 (1975-02-01), Hofvenstan et al.
patent: 3963534 (1976-06-01), Frenkel et al.
Fuel Element Fabrication w/ Special Emphasis on Cladding Materials, "Development of Zircaloy 4," J. N. Chirigos et al., Proceedings of a Symposium held in Vienna, May 10-13, 1960, vol. 1, Academic Press, 1961.
"The Effect of Heat Treatment on the Corrosion Resistance of Zircaloy-2 and Zircaloy-3," J. G. Goodwin, Bettis Technical Review, Jan., 1958, WAPD-BT-6, Bettis Plant, Pittsburg, Pa.
Cox, Journal of Nuclear Materials (28), 1968, pp. 1-47.
Cox, "Accelerated Oxidation of Zircaloy-2 in Supercritical Steam," AECL-4448, Apr., 1973.
Johnson et al., "A Study of Zirconium Alloy Corrosion Parameters in the Advanced Test Reactor," Paper presented Aug. 21-24, 1973, Portland, Oregon, ASTM & AIME.
Johnson, ASTM-STP458, 1969, pp. 271-285.
Kass, ASTM, STP368, 1964, pp. 3-27.

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