aruna devi - Academia.edu (original) (raw)

Uploads

Papers by aruna devi

Research paper thumbnail of Characterization of argon ion irradiation induced changes in microstructure and mechanical property of binary Zr−2.9 wt% Sn alloy

Radiation Physics and Chemistry, 2022

Abstract In this study, we report the investigation of microstructural and mechanical property ch... more Abstract In this study, we report the investigation of microstructural and mechanical property changes in binary Zr−2.9 wt% Sn alloy induced by room temperature heavy ion (Ar9+) irradiation to fluences ranging from 3.1 × 1015 to 4.17 × 1016 Ar9+cm-2. S-parameter, probed using positron annihilation spectroscopy, showed an increase with fluence. Changes in microstructural attributes, viz., the coherently scattering domain size, microstrain, dislocation density and, residual stress, were ascertained through grazing incidence X-ray diffraction. A decrease in domain size and increase in both microstrain and dislocation density were observed in addition to the development of compressive stress in place of tensile after irradiation. The hardness of the irradiated samples, probed by nanoindentation, was found to be higher in comparison to unirradiated one. Transmission electron microscopy investigation exemplified the formation of - and - type dislocation loops upon irradiation. The above findings could be rationalized on the basis of the defects generated during Ar9+ heavy ion irradiation.

Research paper thumbnail of Microstructural investigation of irradiation damage behavior of proton irradiated Zr-1 wt.% Nb fuel cladding alloy

Journal of Nuclear Materials, 2019

Research paper thumbnail of Positron Annihilation Study of Zr-2.5 wt.% Nb alloy Irradiated by Ar9+ heavy ions

Journal of Physics: Conference Series, 2015

Zr-2.5 Nballoy is used as a pressure tube material in pressurized heavy water reactor (PHWR). It ... more Zr-2.5 Nballoy is used as a pressure tube material in pressurized heavy water reactor (PHWR). It is one of the most critical component which decides the lifespan of the reactor. The in-reactor degrading phenomenon of prime concern is dimensional changes caused by irradiation induced creep and growth processes. The present study aims to understand the mechanism of irradiation damage by irradiating the alloy with heavy ion. Such type of irradiation study would facilitate larger damage of material in a shorter time. Zr-2.5Nb alloy samples were irradiated using 315 keV Ar9+ ion for different durations. The irradiation doses were varied in the range of 3.1X1015 to 4.17X1016 Ar9+/cm2. SRIM calculation was carried out to evaluate damage profile in the irradiated samples. Beam based Positron Annihilation Spectroscopy (PAS) technique was used for depth profiling to characterize defect distribution in the alloys. The no. of defects generated is seen to increase with the increase in the fluence.

Research paper thumbnail of Characterization of argon ion irradiation induced changes in microstructure and mechanical property of binary Zr−2.9 wt% Sn alloy

Radiation Physics and Chemistry, 2022

Abstract In this study, we report the investigation of microstructural and mechanical property ch... more Abstract In this study, we report the investigation of microstructural and mechanical property changes in binary Zr−2.9 wt% Sn alloy induced by room temperature heavy ion (Ar9+) irradiation to fluences ranging from 3.1 × 1015 to 4.17 × 1016 Ar9+cm-2. S-parameter, probed using positron annihilation spectroscopy, showed an increase with fluence. Changes in microstructural attributes, viz., the coherently scattering domain size, microstrain, dislocation density and, residual stress, were ascertained through grazing incidence X-ray diffraction. A decrease in domain size and increase in both microstrain and dislocation density were observed in addition to the development of compressive stress in place of tensile after irradiation. The hardness of the irradiated samples, probed by nanoindentation, was found to be higher in comparison to unirradiated one. Transmission electron microscopy investigation exemplified the formation of - and - type dislocation loops upon irradiation. The above findings could be rationalized on the basis of the defects generated during Ar9+ heavy ion irradiation.

Research paper thumbnail of Microstructural investigation of irradiation damage behavior of proton irradiated Zr-1 wt.% Nb fuel cladding alloy

Journal of Nuclear Materials, 2019

Research paper thumbnail of Positron Annihilation Study of Zr-2.5 wt.% Nb alloy Irradiated by Ar9+ heavy ions

Journal of Physics: Conference Series, 2015

Zr-2.5 Nballoy is used as a pressure tube material in pressurized heavy water reactor (PHWR). It ... more Zr-2.5 Nballoy is used as a pressure tube material in pressurized heavy water reactor (PHWR). It is one of the most critical component which decides the lifespan of the reactor. The in-reactor degrading phenomenon of prime concern is dimensional changes caused by irradiation induced creep and growth processes. The present study aims to understand the mechanism of irradiation damage by irradiating the alloy with heavy ion. Such type of irradiation study would facilitate larger damage of material in a shorter time. Zr-2.5Nb alloy samples were irradiated using 315 keV Ar9+ ion for different durations. The irradiation doses were varied in the range of 3.1X1015 to 4.17X1016 Ar9+/cm2. SRIM calculation was carried out to evaluate damage profile in the irradiated samples. Beam based Positron Annihilation Spectroscopy (PAS) technique was used for depth profiling to characterize defect distribution in the alloys. The no. of defects generated is seen to increase with the increase in the fluence.

Log In