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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 1.4919 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.

Additional information

Authors: COEN V, JRC - ISPRA ESTAB. (ITALY);KOLBE H, JRC - ISPRA ESTAB. (ITALY);ORECCHIA L JRC - ISPRA ESTAB. (ITALY), JRC - ISPRA ESTAB. (ITALY)
Bibliographic Reference: THIRD INTERNATIONAL CONFERENCE ON FUSION REACTOR MATERIALS, KARLSRUHE (GERMANY), OCT. 4-8, 1987 WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 33513 ORA
Availability: Can be ordered online
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