Patent · US Expired

Process for forming a chromium oxide insulating layer between the pellets and the cladding of a nuclear fuel element, and fuel element having such an insulating layer

US5137683A · kind A · utility

4Cited by
6References
11Claims
0Family size

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Key dates

Filing dateJul 20, 1990
Grant dateAug 11, 1992
Priority date
Expiry dateJul 20, 2010

Classification

  • Technology area (CPC C)Chemistry; Metallurgy
  • CPC primaryC23C16/405
  • WIPO fieldSurface technology, coating
  • WIPO sectorChemistry

Abstract

An organometallic chromium compound in the gaseous phase is brought into contact with a substrate consisting of the inner surface of the zirconium alloy tubular cladding (5) of the fuel element, or the outer surface of the pellets of fuel material, the substrate being kept at a temperature between 300.degree. and 600.degree. C. The organo metallic compound may consist of chromium acetylacetonate. The process enables a chromium oxide coating to be obtained inside the tubular cladding (5) and/or on the outer surface of the nuclear fuel pellets. Pellet/cladding interaction is thus prevented or limited when this fuel element is used in the reactor.

Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.