Abstract
Experiments were carried out to study the effect of Pb-17Li on the tensile properties of steels considered as candidate structural materials in fusion reactor conceptual designs. In order to investigate a possible LME effect tensile tests, in Pb-17Li at various strain rates and temperatures, were carried out on AISI 316 L, DIN 1.4914 and AMCR. Data on plastic strain at break and the results of fractographic and metallographic analysis are reported. Stress corrosion tests, in Pb-17Li at 723 K for periods of 2500 h were performed on AISI 316 L specimens. After the tests the samples were longitudinally sectioned and different cross sections microscopically examined. The stressed samples are compared to plain specimens heat treated in the liquid alloy in the same experimental conditions.
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