Abstract
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).
| Original language | English (US) |
|---|---|
| Title of host publication | Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors |
| Editors | Denise Paraventi, Michael Wright, John H. Jackson |
| Publisher | Springer International Publishing |
| Pages | 617-635 |
| Number of pages | 19 |
| ISBN (Print) | 9783319672434 |
| DOIs | |
| State | Published - Jan 1 2018 |
| Event | 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017 - Portland, United States Duration: Aug 13 2017 → Aug 17 2017 |
Publication series
| Name | Minerals, Metals and Materials Series |
|---|---|
| Volume | Part F9 |
| ISSN (Print) | 2367-1181 |
| ISSN (Electronic) | 2367-1696 |
Other
| Other | 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017 |
|---|---|
| Country | United States |
| City | Portland |
| Period | 8/13/17 → 8/17/17 |
Fingerprint
Keywords
- Electron back-scattered diffraction
- Nanoindentation stress-strain
- Radiation damage gradient
- Stress saturation
- Transmission electron microscopy
Cite this
Spherical nanoindentation stress-strain analysis of ion-irradiated tungsten. / Pathak, Siddhartha; Weaver, Jordan S.; Sun, Cheng; Wang, Yongqiang; Kalidindi, Surya R.; Mara, Nathan A.
Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. ed. / Denise Paraventi; Michael Wright; John H. Jackson. Springer International Publishing, 2018. p. 617-635 (Minerals, Metals and Materials Series; Vol. Part F9).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution
}
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 - 2018/1/1
Y1 - 2018/1/1
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).
KW - Electron back-scattered diffraction
KW - Nanoindentation stress-strain
KW - Radiation damage gradient
KW - Stress saturation
KW - Transmission electron microscopy
UR - http://www.scopus.com/inward/record.url?scp=85042480367&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=85042480367&partnerID=8YFLogxK
U2 - 10.1007/978-3-319-67244-1_40
DO - 10.1007/978-3-319-67244-1_40
M3 - Conference contribution
SN - 9783319672434
T3 - Minerals, Metals and Materials Series
SP - 617
EP - 635
BT - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
A2 - Paraventi, Denise
A2 - Wright, Michael
A2 - Jackson, John H.
PB - Springer International Publishing
ER -