SYMPOSIA PAPER Published: 01 January 1969

Development of Austenitic Stainless Steels with Improved Resistance to Elevated-Temperature Irradiation Embrittlement


The effects of titanium in concentrations of up to 0.5 weight percent on the tensile and creep-rupture properties of unirradiated and irradiated types 304 and 304L stainless steel have been investigated. It was found that within this range an alloy containing 0.15 to 0.25 weight percent titanium has optimum postirradiation ductility. When this alloy is annealed 1 h at 925 C prior to irradiation, the postirradiation ductility is essentially independent of tension test temperature and increases as the strain rate is reduced in creep-rupture tests at 700 C. In contrast, the postirradiation ductility of standard types 304 or 304L stainless steel heat treated and irradiated under the same conditions decreases with increasing temperature or decreasing strain rate.

These effects appear to result primarily from the effect of titanium on the intergranular fracture process, making crack initiation or propagation, or both, more difficult and thus reducing susceptibility to the high-temperature irradiation embrittlement phenomenon.

Author Information

Bloom, E., E.
Oak Ridge National Laboratory, Oak Ridge, Tennessee
Weir, J., R.
Oak Ridge National Laboratory, Oak Ridge, Tennessee
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Developed by Committee: E10
Pages: 261–289
DOI: 10.1520/STP41851S
ISBN-EB: 978-0-8031-6036-1
ISBN-13: 978-0-8031-6190-0