High Strength Zirconium-Base Alloys

Technical Report · Wed Feb 22 04:00:00 EST 1961

DOI:https://doi.org/10.2172/4031367· OSTI ID:4031367

Henrikson, G. A. ^[1]

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1. Nuclear Metals, Inc., Concord, MA (United States)

An evaluation was made of the mechanical and corrosion properties of certain high-strength zirconium alloys for possible use as structural or fuel element cladding materials. The zirconium alloys studied were prepared by double consumable electrode arc melting followed by extrusion and included: Zr-3 wt% Mo- -2 wt% Al, Zr-5 wt% Mo-2 wt% Al, Zr-7 wt% Mo-2 wt% Al, Zr-1 wt% Mo-5wt% Al, Zr-3wt% Mo-5wt% Al, Zr-7wt% Sn-1.5wt% Al, and Zr-7 wt% Sn-2.5 wt% Al. Tensile measurements at room temperature were made on these alloys as-extruded, solution treated, and after aging at 600°C for 1 tc 1000 hr. In addition, tensile measurements were made at 600°C on samples aged for 1000 hr at 600°C. Corrosion tests in 680°F water (6 days) and 750°F steam (3 days) were made on as-extruded samples. Room temperature yield strength values, elongations at fracture, and yield strength values obtained at 600°C are given. The Zr-5 wt% Mo- 2 wt% Al and Zr-7 wt% Mo-2 wt% Al alloys exhibited some corrosion resistance, whereas the other alloys spalled badly under the test conditions.

• Research Organization: Nuclear Metals, Inc., Concord, MA (United States)
• Sponsoring Organization: US Atomic Energy Commission (AEC)
• NSA Number: NSA-15-023949
• OSTI ID: 4031367
• Report Number(s): NMI--1244
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
ALUMINUM ALLOYS
CORROSION
ELECTRIC ARCS
ELECTRODES
EXTRUSION
FAILURES
FUEL CANS
FUEL ELEMENTS
HEAT TREATMENTS
HIGH TEMPERATURE
MATERIALS TESTING
MEASURED VALUES
MECHANICAL PROPERTIES
MECHANICAL STRUCTURES
MELTING
MOLYBDENUM ALLOYS
PREPARATION
QUANTITY RATIO
SAMPLING
SOLUTIONS
STABILITY
STEAM
TEMPERATURE
TENSILE PROPERTIES
TIN ALLOYS
USES
WATER
ZIRCONIUM ALLOYS