Method of manufacturing cladding tubes of a zirconium-based alloy for fuel rods for nuclear reactors
In the manufacture of cladding tubes of a zirconium-based alloy for fuel rods for nuclear reactors by extrusion of the zirconium-based alloy and cold rollings of the extruded product with annealings, intermediate annealings, between the cold rollings and a b-quenching of the extruded product prior to the last cold rolling, a cladding tube is provided which has at the same time good corrosion properties and mechanical properties by performing the b-quenching prior to a cold rolling, after which an intermediate annealing is performed at a temperature of 500/sup 0/-675/sup 0/ C., and preferably at a temperature of 500/sup 0/-610/sup 0/ C. The zirconium-based alloy is a zirconium-tin alloy comprising 1.2-1.7% tin, 0.07-0.24% iron, 0.05-0.15% chromium and 0-0.08% nickel.
- Assignee:
- Santrade Ltd. (Sweden)
- Patent Number(s):
- US 4450020
- OSTI ID:
- 6149924
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220300* -- Nuclear Reactor Technology-- Fuel Elements
36 MATERIALS SCIENCE
360101 -- Metals & Alloys-- Preparation & Fabrication
ALLOYS
ANNEALING
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
CLADDING
COLD WORKING
CORROSION RESISTANCE
DEPOSITION
EXTRUSION
FABRICATION
FUEL CANS
FUEL ELEMENTS
FUEL RODS
HEAT TREATMENTS
HIGH TEMPERATURE
IRON ADDITIONS
IRON ALLOYS
MATERIALS WORKING
MECHANICAL PROPERTIES
NICKEL ADDITIONS
NICKEL ALLOYS
QUENCHING
REACTOR COMPONENTS
SURFACE COATING
TIN ALLOYS
TUBES
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS