Influence of Ar Implantation on the Precipitation in Au Ion Irradiated AISI 316L Solution Annealed Alloy
- PDF / 582,133 Bytes
- 7 Pages / 432 x 648 pts Page_size
- 118 Downloads / 201 Views
MRS Advances © 2018 Materials Research Society DOI: 10.1557/adv.2018.414
Influence of Ar Implantation on the Precipitation in Au Ion Irradiated AISI 316L Solution Annealed Alloy Ítalo M. Oyarzabal1, Mariana de M. Timm1, Willian M. Pasini2, Franciele S. M. de Oliveira1, Francine Tatsch1, Lívio Amaral1 and Paulo F. P. Fichtner1,2 1
Instituto de Física, Universidade Federal do Rio Grande do Sul, RS, Brazil
2
Departamento de Metalurgia, Universidade Federal do Rio Grande do Sul, RS, Brazil
ABSTRACT
200 μm thick solution annealed AISI 316L stainless steel foils were implanted with Ar ions to produce a 0.25 at. % concentration-depth plateau extending from the near surface to a depth of ≈ 250 nm, and then annealed at 550°C for 2 hours to form small Ar bubbles and Arvacancy clusters. Distinct sets of samples (including control ones without Ar) were irradiated at the temperature of 550 °C with Au ions accelerated at 5 MeV to produce an average damage content about ≈36 dpa at the region containing the Ar plateau. These samples were investigated by transmission electron microscopy using plan-view specimens prepared by ion milling. In contrast with the control samples where the irradiation causes the formation of a high concentration of extended defects and large cavities, carbonite precipitation of 1:1 metal-carbon (MC) content with a cubic structure occurs only in the samples containing the Ar bubbles. This precipitation phenomenon is not commonly observed in the literature. The results are interpreted considering that the precipitate growth process requires the emission of vacancies which are synergistically absorbed by the growth of the Ar bubbles.
1799
Downloaded from https://www.cambridge.org/core. Access paid by the UCSB Libraries, on 21 Jun 2018 at 03:13:04, subject to the Cambridge Core terms of use, available at https://www.cambridge.org/core/terms. https://doi.org/10.1557/adv.2018.414
INTRODUCTION Ion irradiation experiments are often used to provide insights on the irradiation damage effects in materials exposed to a nuclear environment. The simpler approach is to simulate as close as possible the nuclear environment conditions to obtain rather direct predictions to the material endurance limits. A more complex approach implies the understanding of the atomic mechanisms controlling the irradiation induced microstructure evolution processes related to atomic displacements and generation of fission products such as inert gases. In this case, it is necessary to explore distinct irradiation conditions to understand how the atomic mechanisms behave as a function of the irradiation parameters and of the initial target microstructure arrangement [1]. In the present contribution, we report on first results from a more extensive project comprising the use of heavy ion irradiations onto complex alloy systems containing inert gases. As a model case material for the present study, we use a solution annealed AISI 316L stainless steel to investigate the Au+ ion irradiation effects. We use a heavy ion to test for the ef
Data Loading...
