STUDY OF POINT DEFECT PROCESSES IN CANDIDATE AND MODEL ALLOYS FOR FUSION REACTOR FIRST WALL BY HVEM.

T. Yoshiie, S. Kojima, Y. Sato, N. Yoshida, M. Kiritani

Research output: Contribution to conferencePaperpeer-review

Abstract

High-energy electron irradiation on a modified 316 austenitic stainless steel and its model alloys, Fe-Cr-Ni, Fe-Cr-Ni-Ti and Fe-Cr-Ni-Si, and a ferritic steel has been performed with a high-voltage electron microscope. Interstitial-type dislocation loops are formed in all alloys. Comparisons of the nucleation and the growth rate of interstitial loops among four austenitic steels suggests strong interaction between the titanium atoms and vacancies and between the silicon atoms and interstitials. The effect of pre-heat treatment above 600 degree C on the loop nucleation during lower-temperature irradiation has been found, especially near the specimen surface. In ferritic steel, the nucleation of interstitial loops occurs continuously during steady-state irradiation, where the dynamically-balanced state of point defects is established. This difference from pure metals, in general, is attributed to the smaller difference of mobilities between vacancies and interstitials in the steel than that in pure metals.

Original languageEnglish
Pages390-394
Number of pages5
Publication statusPublished - 1985 Dec 1

ASJC Scopus subject areas

  • Engineering(all)

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