Zirconium alloy fuel cladding resistant to pci crack propagation
This patent describes a corrosion and crack resistant water reactor fuel cladding tube comprising: an outer cylindrical layer of a first zirconium alloy selected from the group consisting of Zircaloy-2 and Zircaloy-4; an inner cylindrical layer of a second zirconium alloy consisting essentially of: about 0.1-0.3 wt.% tin, about 0.05 to 0.2 wt.% iron, about 0.05 to 0.4 wt.% niobium, about 0.03 to 0.1 wt.% of an element selected from the group consisting of nickel, chromium and their combinations together, wherein the sum of the iron plus nickel plus chromium contents is less than 0.25 wt.%; less than 2000 ppm total impurities; 300-700 ppm oxygen; and zirconium forming essentially the balance.
- Assignee:
- Westinghouse Electric Corp., Pittsburgh, PA
- Patent Number(s):
- US 4775508
- OSTI ID:
- 6892808
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220300* -- Nuclear Reactor Technology-- Fuel Elements
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
CHEMICAL COMPOSITION
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
CLADDING
CORROSION PROTECTION
CORROSION RESISTANT ALLOYS
DEPOSITION
ENERGY SOURCES
FRACTURE PROPERTIES
FUEL ELEMENTS
FUEL-CLADDING INTERACTIONS
FUELS
IRON ADDITIONS
IRON ALLOYS
IRON COMPOUNDS
MATERIALS
MECHANICAL PROPERTIES
NIOBIUM COMPOUNDS
NUCLEAR FUELS
REACTOR COMPONENTS
REACTOR MATERIALS
REFRACTORY METAL COMPOUNDS
SURFACE COATING
TIN ALLOYS
TRANSITION ELEMENT COMPOUNDS
TUBES
ZIRCALOY
ZIRCALOY 2
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS