Published 1990 | Version v1
Miscellaneous

Elevated temperature tensile properties of Mg-0.8%Al alloy in irradiated and unirradiated condition

Description

In the United Kingdom magnesium alloys have been used in nuclear fuel cladding applications for over 30 years. The mechanical properties of a Mg-0.8%Al alloy have been examined over a range of strain rates at temperatures between 20 and 500 deg C. The variation in ultimate tensile strength, 0.1% proof stress and ductility to failure with test temperature has been evaluated for unirradiated material. These results are compared with data published by other researchers. Similar tests have been carried out on highly irradiated material, machined from actual reactor components, to determine the effect of long term exposure to a neutron flux. Selected irradiated and unirradiated specimens have been examined using optical and scanning electron microscopic techniques to determine the fracture mode. 10 refs.; 15 figs

Additional details

Additional titles

Original title (no language)
Radiatsionnoe materialovedenie. Tom 2.

Publishing Information

Imprint Title
Radiation materials science. V. 2
Imprint Pagination
251 p.
Journal Page Range
p. 88-101.
Report number
INIS-SU--273/A

Conference

Title
International conference on radiation materials science.
Dates
22-25 May 1990.
Place
Alushta (USSR).

INIS

Optional Information

Notes
Imprint:Radiatsionnoe materialovedenie. Tom 2.