Community Research and Development Information Service - CORDIS

Abstract

TENSILE SPECIMENS OF EC REFERENCE 316 STAINLESS STEEL, THE US REFERENCE 316 STAINLESS STEEL, THE US PRIME CANDIDATE ALLOY (PCA) AND THE JAPANESE PRIME CANDIDATE ALLOY WERE IRRADIATED, AFTER SOLUTION ANNEALING OR COLD WORKING, TO DISPLACEMENT LEVELS OF UP TO 10 DPA. BOTH THE IRRADIATED AND THE UNIRRADIATED SPECIMENS WERE TESTED AT THE RESPECTIVE TEMPERATURE OF IRRADIATION IN THE RANGE 523-673 K. THE RESULTS ARE ANALYZED TO DETERMINE THE ROLES OF CHEMISTRY, NEUTRON SPECTRUM, MECHANICAL OR THERMAL HISTORY AND THE TEMPERATURE IN MODIFYING THE DEFORMATION BEHAVIOUR (YIELD STRENGTH, WORK HARDENING RATE AND DUCTILITY) OF THESE MATERIALS DUE TO IRRADIATION. AN ATTEMPT IS MADE TO CORRELATE THESE AND OTHER EXPERIMENTAL OBSERVATIONS ON THE DEFORMATION BEHAVIOUR AFTER IRRADIATION TO THE MICROSTRUCTURAL CHANGES EXPECTED DUE TO IRRADIATION.

Additional information

Authors: TANGRI K, JRC-ISPRA;SCHILLER P JRC-ISPRA, JRC-ISPRA
Bibliographic Reference: PAPER PRESENTED: 3RD INTERNATIONAL CONFERENCE ON FUSION REACTOR MATERIALS, KARLSRUHE/D, OCT. 4-8, 1987. JOURNAL OF NUCLEAR MATERIALS, VOLS. 155-157, PP 1296-1300, 1988
Record Number: 1989126225000 / Last updated on: 1989-04-01
Category: PUBLICATION
Available languages: en