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Primary Examiner: Rutledge, L. Dewayne
Assistant Examiner: Skiff, Peter K.
Attorney: MaLossi; Leo I., Davis, Jr.; James C.

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Title: Zirconium alloy heat treatment process and product

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.

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Other info:

Inventors: Williams, Cedric D. (Wilmington, NC, US)
Urquhart, Andrew W. (Scotia, NY, US)
Walker, James L. (Schenectady, NY, US)
Proebstle, Richard A. (San Jose, CA, US)
Black, Timothy J. (San Jose, CA, US)

Application Number: 852906
Filing Date: 1977-11-18
Publication_date: 1980-12-09
Assignee: General Electric Company (Schenectady, NY)
Primary Class(es): 148/672 148/421, 376/457, 376/900
Other Classes:
US Patent Ref:

2894866	Jul, 1959	Picklesimer	148/11.
3287111	Nov, 1966	Klepfo	75/177.
3865635	Feb, 1975	Hofvenstan et al.	148/11.
3963534	Jun, 1976	Frenkel et al.	148/11.

Other Refs: Other References: 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.