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:10.1007/978-3-030-04639-2_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

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

4 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	Minerals, Metals and Materials Series
Publisher	Springer International Publishing
Pages	617-635
Number of pages	19
ISBN (Print)	9783030046385, 9783030046392, 9783319515403, 9783319651354, 9783319728520, 9783319950211
DOIs	https://doi.org/10.1007/978-3-030-04639-2_40
State	Published - 2019
Event	18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019 - Boston, United States Duration: Aug 18 2019 → Aug 22 2019

Publication series

Name	Minerals, Metals and Materials Series
ISSN (Print)	2367-1181
ISSN (Electronic)	2367-1696

Conference

Conference	18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019
Country/Territory	United States
City	Boston
Period	8/18/19 → 8/22/19

Bibliographical note

Funding Information:
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:
© 2019, The Minerals, Metals & Materials Society.

Keywords

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

Publisher link

10.1007/978-3-030-04639-2_40

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Pathak, S, Weaver, JS, Sun, C, Wang, Y, Kalidindi, SR & Mara, NA 2019, Spherical nanoindentation stress-strain analysis of ion-irradiated tungsten. in Minerals, Metals and Materials Series. Minerals, Metals and Materials Series, Springer International Publishing, pp. 617-635, 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019, Boston, United States, 8/18/19. https://doi.org/10.1007/978-3-030-04639-2_40

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title = "Spherical nanoindentation stress-strain analysis of ion-irradiated tungsten",

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).",

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

author = "Siddhartha Pathak and Weaver, {Jordan S.} and Cheng Sun and Yongqiang Wang and Kalidindi, {Surya R.} and Mara, {Nathan A.}",

note = "Funding Information: 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{\textquoteright}s Postdoctoral Fellowship and University of Nevada, Reno start-up faculty funds for this work. Publisher Copyright: {\textcopyright} 2019, The Minerals, Metals & Materials Society.; 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019 ; Conference date: 18-08-2019 Through 22-08-2019",

year = "2019",

doi = "10.1007/978-3-030-04639-2_40",

language = "English (US)",

isbn = "9783030046385",

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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.

N1 - Funding Information: 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: © 2019, The Minerals, Metals & Materials Society.

PY - 2019

Y1 - 2019

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

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U2 - 10.1007/978-3-030-04639-2_40

DO - 10.1007/978-3-030-04639-2_40

M3 - Conference contribution

AN - SCOPUS:85064066872

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 - Springer International Publishing

T2 - 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019

Y2 - 18 August 2019 through 22 August 2019

ER -

Spherical nanoindentation stress-strain analysis of ion-irradiated tungsten

Abstract

Publication series

Conference

Bibliographical note

Keywords

Publisher link

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