Spherical nanoindentation stress-strain analysis of ion-irradiated tungsten

Siddhartha Pathak; Jordan S. Weaver; Cheng Sun; Yongqiang Wang; Surya R. Kalidindi; Nathan A. Mara

doi:10.1007/978-3-319-67244-1_40

Spherical nanoindentation stress-strain analysis of ion-irradiated tungsten

Siddhartha Pathak, Jordan S. Weaver, Cheng Sun, Yongqiang Wang, Surya R. Kalidindi, Nathan A. Mara

Chemical Engineering and Materials Science

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

2 Scopus citations

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	https://doi.org/10.1007/978-3-319-67244-1_40
State	Published - 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/Territory	United States
City	Portland
Period	8/13/17 → 8/17/17

Bibliographical note

Funding Information:
Acknowledgements The authors acknowledge funding from Department of Energy, Nuclear Engineering Enabling Technologies (DOE-NEET)—Reactor Materials program # DE-FOA-0000799, and University of California Office of the President (UCOP) under Award Number 12—LR237801 for this work. This work was performed, in part, at the Center for Integrated Nanotechnologies, an Office of Science User Facility operated for the U.S. Department of Energy (DOE) Office of Science. Los Alamos National Laboratory, an affirmative action equal opportunity employer, is operated by Los Alamos National Security, LLC, for the National Nuclear Security Administration of the U.S. Department of Energy under contract DE-AC52-06NA25396. SP gratefully acknowledges funding from the Los Alamos National Laboratory Director’s Postdoctoral Fellowship and University of Nevada, Reno start-up faculty funds for this work.

Publisher Copyright:
© The Minerals, Metals & Materials Society 2018.

Keywords

Electron back-scattered diffraction
Nanoindentation stress-strain
Radiation damage gradient
Stress saturation
Transmission electron microscopy

Publisher link

10.1007/978-3-319-67244-1_40

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Pathak, S., Weaver, J. S., Sun, C., Wang, Y., Kalidindi, S. R., & Mara, N. A. (2018). Spherical nanoindentation stress-strain analysis of ion-irradiated tungsten. In D. Paraventi, M. Wright, & J. H. Jackson (Eds.), Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors (pp. 617-635). (Minerals, Metals and Materials Series; Vol. Part F9). Springer International Publishing. https://doi.org/10.1007/978-3-319-67244-1_40

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

Pathak, S, Weaver, JS, Sun, C, Wang, Y, Kalidindi, SR & Mara, NA 2018, Spherical nanoindentation stress-strain analysis of ion-irradiated tungsten. in D Paraventi, M Wright & JH Jackson (eds), Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Minerals, Metals and Materials Series, vol. Part F9, Springer International Publishing, pp. 617-635, 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017, Portland, United States, 8/13/17. https://doi.org/10.1007/978-3-319-67244-1_40

Pathak S, Weaver JS, Sun C, Wang Y, Kalidindi SR, Mara NA. Spherical nanoindentation stress-strain analysis of ion-irradiated tungsten. In Paraventi D, Wright M, Jackson JH, editors, Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Springer International Publishing. 2018. p. 617-635. (Minerals, Metals and Materials Series). https://doi.org/10.1007/978-3-319-67244-1_40

Pathak, Siddhartha ; Weaver, Jordan S. ; Sun, Cheng ; Wang, Yongqiang ; Kalidindi, Surya R. ; Mara, Nathan A. / Spherical nanoindentation stress-strain analysis of ion-irradiated tungsten. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. editor / Denise Paraventi ; Michael Wright ; John H. Jackson. Springer International Publishing, 2018. pp. 617-635 (Minerals, Metals and Materials Series).

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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).",

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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).

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ER -

Spherical nanoindentation stress-strain analysis of ion-irradiated tungsten

Abstract

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Bibliographical note

Keywords

Publisher link

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