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Spherical Nanoindentation Stress-Strain Analysis of Ion-Irradiated Tungsten

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Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors

Part of the book series: The Minerals, Metals & Materials Series ((MMMS))

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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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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.

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Author notes

  1. Cheng Sun

    Present address: Idaho National Laboratory, Idaho Falls, 83415, USA

Authors and Affiliations

  1. Chemical and Materials Engineering, University of Nevada, 1664 N Virginia St., Mail Stop 0388, Reno, NV, 89557, USA

    Siddhartha Pathak

  2. Los Alamos National Laboratory, Center for Integrated Nanotechnologies, Los Alamos, NM, 87545, USA

    Jordan S. Weaver & Nathan A. Mara

  3. Materials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM, 87545, USA

    Cheng Sun, Yongqiang Wang & Nathan A. Mara

  4. George W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, GA, 30332, USA

    Surya R. Kalidindi

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  1. Siddhartha Pathak
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  2. Jordan S. Weaver
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  3. Cheng Sun
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  4. Yongqiang Wang
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  5. Surya R. Kalidindi
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  6. Nathan A. Mara
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Correspondence to Siddhartha Pathak .

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Editors and Affiliations

  1. Idaho National Laboratory, Idaho Falls, ID, USA

    John H. Jackson

  2. Naval Nuclear Laboratory, Pittsburgh, PA, USA

    Denise Paraventi

  3. Chalk River Laboratories, Canadian Nuclear Laboratories, Chalk River, ON, Canada

    Michael Wright

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Pathak, S., Weaver, J.S., Sun, C., Wang, Y., Kalidindi, S.R., Mara, N.A. (2019). Spherical Nanoindentation Stress-Strain Analysis of Ion-Irradiated Tungsten. In: Jackson, J., Paraventi, D., Wright, M. (eds) Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The Minerals, Metals & Materials Series. Springer, Cham. https://doi.org/10.1007/978-3-030-04639-2_40

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