Zirconium alloy fuel cladding resistant to PCI crack propagation
A nuclear fuel element is described cladding tube comprising: concentric tubular layers of zirconium base alloys; the concentric tubular layers including an inner layer and outer layer; the outer layer metallurgically bonded to the inner layer; the outer layer composed of a first zirconium base alloy characterized by excellent resistance to corrosion caused by exposure to high temperature and pressure aqueous environments; the inner layer composed of a second zirconium base alloy consisting of: about 0.2 to 0.6 wt.% tin, about 0.03 to 0.11 wt.% iron, less than about 0.02 wt.% chromium, up to about 350 ppm oxygen and the remainder being zirconium and incidental impurities, and the inner layer characterized by improved resistance to crack propagation under reactor operating conditions compared to the first zirconium alloy.
- Assignee:
- Westinghouse Electric Corp., Pittsburgh, PA
- Patent Number(s):
- US 4675153
- OSTI ID:
- 6434475
- Country of Publication:
- United States
- Language:
- English
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Zirconium base fuel cladding resistant to PCI crack propagation
Related Subjects
220300* -- Nuclear Reactor Technology-- Fuel Elements
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
BONDING
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
CORROSION RESISTANCE
CRACK PROPAGATION
ECCS
ELEMENTS
ENGINEERED SAFETY SYSTEMS
FABRICATION
FUEL CANS
FUEL ELEMENTS
IMPURITIES
IRON ADDITIONS
IRON ALLOYS
JOINING
LAYERS
METALLURGY
NONMETALS
OPERATION
OXYGEN
PRESSURE EFFECTS
REACTOR COMPONENTS
REACTOR OPERATION
REACTOR PROTECTION SYSTEMS
TEMPERATURE EFFECTS
TIN ADDITIONS
TIN ALLOYS
TUBES
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS