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.
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.