TY - GEN
T1 - Spherical nanoindentation stress-strain analysis of ion-irradiated tungsten
AU - Pathak, Siddhartha
AU - Weaver, Jordan S.
AU - Sun, Cheng
AU - Wang, Yongqiang
AU - Kalidindi, Surya R.
AU - Mara, Nathan A.
PY - 2019/1/1
Y1 - 2019/1/1
N2 - This paper discusses applications of spherical nanoindentation stress-strain curves in characterizing the local mechanical behavior of materials with modified surfaces. Using ion-irradiated tungsten as a specific example, this paper demonstrates that a simple variation of the indenter size (radius) can identify the depth of the radiation-induced-damage zone, as well as quantify the behavior of the damaged zone itself. Using corresponding local structure information from electron backscatter diffraction (EBSD) and transmission electron microscopy (TEM) we look at (a) the elastic response, elasto-plastic transition, and onset of plasticity in ion-irradiated tungsten, zirconium and 304 stainless steel under indentation, and compare their relative mechanical behavior to the unirradiated state, (b) correlating these changes to the different grain orientations as a function of (c) irradiation from different sources (such as He, W, and He+W for tungsten samples).
AB - This paper discusses applications of spherical nanoindentation stress-strain curves in characterizing the local mechanical behavior of materials with modified surfaces. Using ion-irradiated tungsten as a specific example, this paper demonstrates that a simple variation of the indenter size (radius) can identify the depth of the radiation-induced-damage zone, as well as quantify the behavior of the damaged zone itself. Using corresponding local structure information from electron backscatter diffraction (EBSD) and transmission electron microscopy (TEM) we look at (a) the elastic response, elasto-plastic transition, and onset of plasticity in ion-irradiated tungsten, zirconium and 304 stainless steel under indentation, and compare their relative mechanical behavior to the unirradiated state, (b) correlating these changes to the different grain orientations as a function of (c) irradiation from different sources (such as He, W, and He+W for tungsten samples).
UR - https://www.scopus.com/pages/publications/85064066872
U2 - 10.1007/978-3-030-04639-2_40
DO - 10.1007/978-3-030-04639-2_40
M3 - Conference contribution
SN - 9783030046385
SN - 9783030046392
SN - 9783319515403
SN - 9783319651354
SN - 9783319728520
SN - 9783319950211
T3 - Minerals, Metals and Materials Series
SP - 617
EP - 635
BT - Minerals, Metals and Materials Series
PB - Unknown Publisher
T2 - 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019
Y2 - 1 January 2019
ER -