← Back to Patent Explorer
US4473410A Expired / Lapsed US ⏱️ 0.0 years remaining

Nuclear fuel element having a composite coating

Assignee: General Electric Co
•
Filing: 1981-10-05
•
Granted: 1984-09-25
•
Expires: 2001-10-05
📄 Original PDF 🌐 Google Patents 🔄 Sync Now

Abstract

Abstract A nuclear fuel element consisting of a zirconium or zirconium alloy container and nuclear fuel pellets is provided for use in the core of a nuclear reactor. The zirconium or zirconium alloy container has an inner coating of copper in proximity to the nuclear fuel, and is separated from the zirconium or zirconium alloy by an intermediate zirconium oxide diffusion barrier layer. The copper layer and the intermediate zirconium oxide diffusion barrier of the composite cladding reduce perforations or failure in the zirconium or zirconium alloy cladding substrate caused by stress corrosion cracking or metal embrittlement. Good bonding of the copper to the oxide zirconium and zirconium alloy prevents scaling of copper from the composite cladding during the loading of the fuel element with fuel pellets.

Inventors

  • 👤 Willard T. Grubb
  • 👤 Lawrence H. King

Bibliographic Details

Application Number —
Jurisdiction US
Data Source google_patents
Last Synchronized 2026-11-10 00:42
CPC Classifications
G; G21; G21C; G21C3/00; G21C3/02; G21C3/04; G21C3/16; G21C3/20; Y; Y02; Y02E; Y02E30/00; Y02E30/30

Claims Analysis

Total Claims: 5
Claim 1
Independent Claim 103 words
A method for preventing stress corrosion cracking or metal embrittlement of a zirconium or zirconium alloy container useful for holding nuclear fuel material to provide for the production of an improved nuclear fuel element, which comprises (1) roughening the surface of the zirconium or zirconium alloy container by mechanical attrition, (2) oxidizing the resulting zirconium or zirconium alloy container, (3) activating the oxidized surface of (2) to allow for the metallic coating of such surface by electroless deposition, and (4) further coating the activated-oxidized surface of the zirconium or zirconium alloy container of (3) with a metal selected from copper, iron and nickel.
Claim 2
Independent Claim 103 words
A method for preventing stress corrosion cracking or metal embrittlement of a zirconium or zirconium alloy container useful for holding nuclear fuel material to provide for the production of an improved nuclear fuel element, which comprises (1) roughening the surface of the zirconium or zirconium alloy container by mechanical attrition, (2) oxidizing the resulting zirconium or zirconium alloy container, (3) activating the oxidized surface of (2) to allow for the metallic coating of such surface by electroless deposition, and (4) further coating the activated-oxidized surface of the zirconium or zirconium alloy container of (3) with a metal selected from copper, iron and nickel.
Claim 3
Dependent Claim 17 words
A method in accordance with claim 1, where the zirconium oxide surface is electroless plated with copper.
Claim 4
Dependent Claim 22 words
A method in accordance with claim 1, where the oxidizing is achieved by heating the zirconium alloy in steam at elevated temperatures.
Claim 5
Dependent Claim 22 words
A method in accordance with claim 1, where oxidation of the zirconium alloy is effected in an oxygen atmosphere at elevated temperatures.

References Cited (Backward Citations)

US3620691A Cited
US3556870A Cited
US4022662A Cited
US4093756A Cited

USPTO Annuity & Maintenance Windows

Annuity Stage Window Opens Payment Deadline Surcharge Period Until Estimated Fee Status
3.5 Years (Year 4) 1987-09-25 1988-03-26 1988-09-25 $2000.00 Window Closed / Lapsed
7.5 Years (Year 8) 1991-09-25 1992-03-26 1992-09-25 $3760.00 Window Closed / Lapsed
11.5 Years (Year 12) 1995-09-25 1996-03-26 1996-09-25 $7700.00 Window Closed / Lapsed

Assigned Categories & Tags

No categories assigned to this patent yet.

Assign Category Tag