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US4775508A Expired / Lapsed US ⏱️ 0.0 years remaining

Zirconium alloy fuel cladding resistant to PCI crack propagation

Assignee: Westinghouse Electric Co LLC
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Filing: 1987-12-08
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Granted: 1988-10-04
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Expires: 2007-12-08
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Abstract

Abstract This invention relates to a tubular water reactor fuel cladding having an outer cylindrical layer composed of a conventional zirconium base alloy. Bonded to the outer layer is a second, inner layer composed of an alloy consisting essentially of: about 0.1 to 0.3 wt. % tin; about 0.05 to 0.2 wt. % iron; about 0.05 to 0.4 wt. % niobium; about 0.03 to 0.1 wt. % of either chromium or nickel, alone or in combination with each other; while keeping the sum of the iron chromium and nickel contents below 0.25 wt. %; 300 to 1200 ppm oxygen; and the balance essentially zirconium. The inner layer is characterized by excellent resistance to PCI crack propagation, excellent aqueous corrosion resistance and a fully recrystallized microstructure.

Inventors

  • 👤 George P. Sabol
  • 👤 Samuel G. McDonald III

Bibliographic Details

Application Number —
Jurisdiction US
Data Source google_patents
Last Synchronized 2026-11-09 22:47
CPC Classifications
G; G21; G21C; G21C3/00; G21C3/02; G21C3/04; G21C3/06; G21C3/07; Y; Y02; Y02E; Y02E30/00; Y02E30/30

Claims Analysis

Total Claims: 7
Claim 1
Independent Claim 144 words
A corrosion and crack resistant water reactor fuel cladding tube comprising: an outer cylindrical layer of a first zirconium alloy selected from the group consisting of Zircaloy-2 and Zircaloy-4; an inner cylindrical layer of a second zirconium alloy consisting essentially of: about 0.1-0.3 wt.% tin, about 0.05 to 0.2 wt.% iron, about 0.05 to 0.4 wt.% niobium, about 0.03 to 0.1 wt.% of an element selected from the group consisting of nickel, chromium and their combinations together, wherein the sum of the iron plus nickel plus chromium contents is less than 0.25 wt.%; less than 2000 ppm total impurities; 30- 700ppm oxygen; and zirconium forming essentially the balance; said inner cylindrical layer metallurgically bonded to said outer layer; and whereby said inner cylindrical layer has an aqueous corrosion resistance which is at least substantially equivalent to the corrosion resistance of said outer cylindrical layer.
Claim 2
Dependent Claim 144 words
A corrosion and crack resistant water reactor fuel cladding tube comprising: an outer cylindrical layer of a first zirconium alloy selected from the group consisting of Zircaloy-2 and Zircaloy-4; an inner cylindrical layer of a second zirconium alloy consisting essentially of: about 0.1-0.3 wt.% tin, about 0.05 to 0.2 wt.% iron, about 0.05 to 0.4 wt.% niobium, about 0.03 to 0.1 wt.% of an element selected from the group consisting of nickel, chromium and their combinations together, wherein the sum of the iron plus nickel plus chromium contents is less than 0.25 wt.%; less than 2000 ppm total impurities; 30- 700ppm oxygen; and zirconium forming essentially the balance; said inner cylindrical layer metallurgically bonded to said outer layer; and whereby said inner cylindrical layer has an aqueous corrosion resistance which is at least substantially equivalent to the corrosion resistance of said outer cylindrical layer.
Claim 3
Dependent Claim 30 words
The water reactor fuel cladding tube according to claim 1 wherein said second zirconium alloy has nickel content of 0.03-0.1 wt.% and a chromium content of less than 200 ppm.
Claim 4
Dependent Claim 33 words
The water reactor fuel cladding tube according to claim 1 wherein said second zirconium alloy has a chromium content of 0.03 to -0.1 wt.%, and a nickel content of less than 70 ppm.
Claim 5
Dependent Claim 24 words
The water reactor fuel cladding tube according to claim 1 wherein said second zironium alloy has a niobium content of 0.05 to 0.2 wt.%.
Claim 6
Dependent Claim 46 words
The water reactor fuel cladding tube according to claim 1 having a weight gain of less than 200 mg/dm 2 and an essentially black, adherent oxide film on said inner and said outer layers after 24 hours exposure to a 500° C. 1500 psi steam test.
Claim 7
Dependent Claim 20 words
The water reactor fuel cladding tube according to claim 1 wherein said inner cylindrical layer has a fully recrystallized microstructure.

USPTO Annuity & Maintenance Windows

Annuity Stage Window Opens Payment Deadline Surcharge Period Until Estimated Fee Status
3.5 Years (Year 4) 1991-10-04 1992-04-04 1992-10-04 $2000.00 Window Closed / Lapsed
7.5 Years (Year 8) 1995-10-04 1996-04-04 1996-10-04 $3760.00 Window Closed / Lapsed
11.5 Years (Year 12) 1999-10-04 2000-04-04 2000-10-04 $7700.00 Window Closed / Lapsed

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