Micro-mechanics of irradiated Fe-Cr alloys for fusion reactors

作者: Christopher David Hardie

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摘要: In the absence of a fusion neutron source, research on structural integrity materials in environment relies current fission data and simulation methods. Through investigation Fe-Cr system, this detailed study explores challenges limitations use currently available radiation sources for research. An ion-irradiated Fe12%Cr using nanoindentation with cube corner, Berkovich spherical tip, micro-cantilever testing two different geometries, highlighted that measurement irradiation hardening was largely dependent type test used. Selected methods were used comparison Fe6%Cr irradiated by ions neutrons to dose 1.7dpa at temperature 288°C. Micro-cantilever tests alloy beam depths 400 7000nm, identified size effects may significantly obscure these are conditions. Irradiation neutron-irradiated approximately double exhibited increased work hardening. Similar differences observed an Fe5%Cr after ion-irradiation 0.6dpa 400°C doses rates 6 x 10-4dpa/s 3 10-5dpa/s. Identified APT, it shown likely be caused enhanced segregation Cr lower rate. These observations have significant implications future terms relevant conditions micro-mechanical testing.

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