Electroless deposition process for zirconium and zirconium alloys

Patent · Tue Aug 18 04:00:00 EDT 1981

OSTI ID:7249433

Donaghy, R. E.; Sherman, A. H.

A method is disclosed for preventing stress corrosion cracking or metal embrittlement of a zirconium or zirconium alloy container that is to be coated on the inside surface with a layer of a metal such as copper, a copper alloy, nickel, or iron and used for holding nuclear fuel material as a nuclear fuel element. The zirconium material is etched in an etchant solution, desmutted mechanically or ultrasonically, oxidized to form an oxide coating on the zirconium, cleaned in an aqueous alkaline cleaning solution, activated for electroless deposition of a metal layer and contacted with an electroless metal plating solution. This method provides a boundary layer of zirconium oxide between the zirconium container and the metal layer. 1 fig.

• Research Organization: General Electric Co., San Jose, CA (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: EN-77-C-02-4473
• Assignee: General Electric Co., San Jose, CA (United States)
• Patent Number(s): US 4284660; A
• Application Number: PPN: US 5-904783
• OSTI ID: 7249433
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220300 -- Nuclear Reactor Technology-- Fuel Elements
36 MATERIALS SCIENCE
360101* -- Metals & Alloys-- Preparation & Fabrication
ALLOYS
CHALCOGENIDES
DEPOSITION
ELEMENTS
ETCHING
FABRICATION
FUEL ELEMENTS
METALS
OXIDES
OXYGEN COMPOUNDS
PLATING
REACTOR COMPONENTS
SURFACE COATING
SURFACE FINISHING
TRANSITION ELEMENT COMPOUNDS
TRANSITION ELEMENTS
ZIRCONIUM
ZIRCONIUM ALLOYS
ZIRCONIUM COMPOUNDS
ZIRCONIUM OXIDES