4.7 Article

In-situ ion irradiation study of alloy 709 stainless steels with different processing histories

Journal

JOURNAL OF NUCLEAR MATERIALS
Volume 553, Issue -, Pages -

Publisher

ELSEVIER
DOI: 10.1016/j.jnucmat.2021.153052

Keywords

Stainless steel; Ion irradiation; in-situ experiment; Mechanical deformation; Electron microscopy

Funding

  1. Advanced Reactor Technologies program from the U.S. Department of Energy, Office of Nuclear Energy [DE-AC02-06CH11357]
  2. DOE, Office of Nuclear Energy, under DOE Idaho Operations Office Contract, Nuclear Science User Facilities [DE-AC07-051D14517]
  3. DOE, Office of Science, Office of Basic Energy Sciences [DE-AC02-06CH11357]

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The study found that Alloy 709 stainless steel samples with different processing histories exhibit varying microstructural changes under high temperature irradiation, with creep-deformed samples showing the smallest dislocation loop size and lowest loop density. The sink strength factors in each sample play a role in influencing these changes.
Alloy 709 stainless steel (A709 SS) has gained an increased interest in nuclear applications due to its advanced properties at high temperatures over the widely used Type 316 SS. However, how this alloy behaves under irradiation with concurrent environmental factors, such as mechanical deformation and/or thermal annealing, has not been studied. In this work, we used in-situ ion irradiation inside a transmission electron microscope (TEM) to investigate the effects of irradiation on the microstructures of A709 SS samples with different prior processing histories, including as-received, annealed, and creep-deformed. It was found that, compared to room temperature irradiation, 600 degrees C irradiation led to larger dislocation loop sizes and lower loop densities. With 600 degrees C irradiation, the creep-deformed sample, which had the highest precipitate density and the highest dislocation density, had the smallest loop size and the lowest loop density compared to others. This observation has been rationalized with quantitative evaluation of the sink strength factors in each sample. This study shows that in-service deformation can significantly affect the irradiation performance in structural materials at reactor operating conditions. (c) 2021 Elsevier B.V. All rights reserved.

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