Thermal-mechanical treatment of composite nuclear fuel...

Details Thermal-mechanical treatment of composite nuclear fuel... Thermal-mechanical treatment of composite nuclear fuel...

G - Physics

21

C

26/196, 359/67

G21C 3/04 (2006.01) G21C 3/20 (2006.01) G21C 21/02 (2006.01)

Patent

CA 1139023

24-NT-04337 ABSTRACT OF THE DISCLOSURE Cladding for nuclear fuel elements which is formed with a zirconium metal barrier layer bonded to the inside surface of a zirconium alloy tube and which is sized by a cold working tube reduction process and is heat treated after final reduction at a temperature and for a time period which allows substantially complete recrystallization of the zirconium metal barrier layer and provides a fine- grained microstructure therein and which stress-relieves but does not fully recrystallize the zirconium alloy tube. The crystallographic structure of the zirconium metal barrier layer may be improved by compressive deformation such as shot-peening.

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