TUBE EN ALLIAGE DE ZIRCONIUM A GRADIENT METALLURGIQUE ET PROCEDE DE FABRICATION

TUBE EN ALLIAGE DE ZIRCONIUM A GRADIENT METALLURGIQUE ET PROCEDE DE FABRICATION

There is provided a nuclear fuel element having a zirconium alloy cladding tube with improved corrosion resistance. The cladding tube comprises a metallurgical gradient across the width of the tube wall wherein the tube has a more corrosion-resistant metallurgical condition at the outer circumferenc...

Ausführliche Beschreibung

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Bibliographische Detailangaben
1. Verfasser: FLETCHER CALVIN EDDENS, DAVID WILLIAM WHITE ET JOHN LEE HARMON
Format: Patent
Sprache:fre
Schlagworte:
CHANGING THE PHYSICAL STRUCTURE OF NON-FERROUS METALS ANDNON-FERROUS ALLOYS
CHEMISTRY
FERROUS OR NON-FERROUS ALLOYS
METALLURGY
NUCLEAR ENGINEERING
NUCLEAR PHYSICS
NUCLEAR REACTORS
PHYSICS
TREATMENT OF ALLOYS OR NON-FERROUS METALS
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Beschreibung
Zusammenfassung:There is provided a nuclear fuel element having a zirconium alloy cladding tube with improved corrosion resistance. The cladding tube comprises a metallurgical gradient across the width of the tube wall wherein the tube has a more corrosion-resistant metallurgical condition at the outer circumference and a less corrosion-resistant metallurgical condition at the inner circumference. The metallurgical gradient can be generated by heating an outer circumferential portion of the tube to the high alpha or mixed alpha plus beta range while maintaining the inner surface at a lower temperature, followed by cooling of the tube.