G - Physics – 21 – C
Patent
G - Physics
21
C
359/82
G21C 3/06 (2006.01) B32B 15/01 (2006.01) C22C 16/00 (2006.01) G21C 3/20 (2006.01)
Patent
CA 1198231
ZIRCONIUM ALLOY BARRIER HAVING IMPROVED CORROSION RESISTANCE ABSTRACT OF THE DISCLOSURE A nuclear fuel element for use in the core of a nuclear reactor which has a composite cladding container having a substrate and a dilute zirconium alloy liner bonded to the inside surface of the substrate. The dilute zirconium alloy liner forms about 1 to about 20 percent of the thickness of the cladding and comprises from about 0.1% to about 0.5% by weight niobium and preferably from about 0.2% to about 0.4% by weight niobium, the balance being zirconium. The dilute zirconium alloy liner shields the substrate from impurities or fissin products from the nuclear fuel material and protects the substrate from stress corrosion and stress cracking. The dilute zirconium alloy liner displays greater corrosion resistance, especially to oxidation by hot water and steam than unalloyed zirconium. The substrate material is selected from conventional cladding materials, and preferably is a zirconium alloy having a higher alloy content than the dilute zirconium alloy liner.
423387
Company General Electric
Eckersley Raymond A.
LandOfFree
Zirconium alloy barrier having improved 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 barrier having improved corrosion resistance, we encourage you to share that experience with our LandOfFree.com community. Your opinion is very important and Zirconium alloy barrier having improved corrosion resistance will most certainly appreciate the feedback.
Profile ID: LFCA-PAI-O-1187060