Journal
JOURNAL OF NUCLEAR MATERIALS
Volume 578, Issue -, Pages -Publisher
ELSEVIER
DOI: 10.1016/j.jnucmat.2023.154309
Keywords
In-situ TEM; Dislocation loop; Fe plus irradiation; Austenitic stainless steel
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This study investigates the evolution processes and characteristics of dislocation loops in HR3 steel under irradiation at different temperatures. The results show that irradiated samples at higher temperatures have larger average size and lower density of dislocation loops. The pre-existing dislocation lines have a significant impact on the density and Burgers vector of dislocation loops.
The evolution and characteristics of dislocation loops, which are affected by the value of temperature play a crucial role in the mechanical properties of structural materials. This study explores the evolution pro-cesses of the dislocation loops with the increasing values of the temperature, and the effect of precipitate on the dislocation loop. In-situ TEM experimental observations are performed using HR3 steel, which is commonly used as a structural material in nuclear reactors, during 400 keV Fe+ irradiation at room tem-perature (RT), 300 degrees C, 400 degrees C and 500 degrees C. The evolution of the dislocation loop at different values of the temperature is characterized in detail. The average size and density of dislocation loops as a function of displacement per atom (dpa) and values of temperature were constructed and analyzed comparatively. Irradiated samples at higher temperatures have a larger average size and a lower density of dislocation loops. The pre-existing dislocation lines have a profound effect on the density and Burgers vector of dis-location loops. Our present results provide a fundamental insight into the evolution and characteristics of dislocation loops in HR3 steel in a gradually changing of temperature environment.(c) 2023 Elsevier B.V. All rights reserved.
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