Elevated temperature tensile properties of Mg-0.8%Al alloy in irradiated and unirradiated condition
Creators
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
- Country of Publication
- USSR
- Country of Input or Organization
- USSR
- INIS RN
- 22075916
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLADDING; FRACTURES; FUEL CANS; HIGH TEMPERATURE; MAGNOX; MECHANICAL PROPERTIES; NEUTRONS; PHYSICAL RADIATION EFFECTS; RADIATION FLUX; SPENT FUEL ELEMENTS
- Descriptors DEC
- ALLOYS; BARYONS; DEPOSITION; ELEMENTARY PARTICLES; FAILURES; FERMIONS; FUEL ELEMENTS; HADRONS; MAGNESIUM ALLOYS; MAGNESIUM BASE ALLOYS; NUCLEONS; RADIATION EFFECTS; REACTOR COMPONENTS; SURFACE COATING
Optional Information
- Notes
- Imprint:Radiatsionnoe materialovedenie. Tom 2.