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Title: Quantifying the mechanical effects of He, W and He + W ion irradiation on tungsten with spherical nanoindentation

Abstract

Here, recent advances in spherical nanoindentation protocols have proven very useful for capturing the grain-scale mechanical response of different metals. This is achieved by converting the load–displacement response into an effective indentation stress–strain response which reveals latent information such as the elastic–plastic transition or indentation yield strength and work-hardening behavior and subsequently correlating the response with the material structure (e.g., crystal orientation) at the indentation site. Using these protocols, we systematically study and quantify the microscale mechanical effects of He, W, and He + W ion irradiation on commercially pure, polycrystalline tungsten. The indentation stress–strain response is correlated with the crystal orientation from electron backscatter diffraction, the defect structure from transmission electron microscopy micrographs, and the stopping range of ions in matter calculations of displacement damage and He concentration. He-implanted grains show a much higher indentation yield strength and saturation stress compared to W-ion-irradiated grains for the same displacement damage. There is also good agreement between the dispersed barrier hardening model with a barrier strength of 0.5–0.8 and void models (Bacon–Kochs–Scattergood and Osetsky–Bacon models) with the experimentally observed changes in indentation strength due to the presence of He bubbles. This finding indicates that a high density (~ 9 × 1023more » m–3) and concentration (~ 1.5 at.%) of small (~ 1 nm diameter) He bubbles can be moderate to strong barriers to dislocation slip in tungsten.« less

Authors:
ORCiD logo [1];  [2]; ORCiD logo [1];  [3];  [4]; ORCiD logo [1];  [5]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  2. Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Idaho National Lab. (INL), Idaho Falls, ID (United States)
  3. Georgia Inst. of Technology, Atlanta, GA (United States)
  4. Univ. of California at San Diego, La Jolla, CA (United States)
  5. Univ. of Nevada, Reno, NV (United States)
Publication Date:
Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1415419
Report Number(s):
LA-UR-17-27921
Journal ID: ISSN 0022-2461; TRN: US1800813
Grant/Contract Number:  
AC52-06NA25396
Resource Type:
Accepted Manuscript
Journal Name:
Journal of Materials Science
Additional Journal Information:
Journal Volume: 53; Journal Issue: 7; Journal ID: ISSN 0022-2461
Publisher:
Springer
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; helium; bubbles; fusion reactor materials; nanomechanical; gradients

Citation Formats

Weaver, Jordan S., Sun, Cheng, Wang, Yongqiang, Kalidindi, Surya R., Doerner, Russ P., Mara, Nathan Allan, and Pathak, Siddhartha. Quantifying the mechanical effects of He, W and He + W ion irradiation on tungsten with spherical nanoindentation. United States: N. p., 2017. Web. doi:10.1007/s10853-017-1833-8.
Weaver, Jordan S., Sun, Cheng, Wang, Yongqiang, Kalidindi, Surya R., Doerner, Russ P., Mara, Nathan Allan, & Pathak, Siddhartha. Quantifying the mechanical effects of He, W and He + W ion irradiation on tungsten with spherical nanoindentation. United States. https://doi.org/10.1007/s10853-017-1833-8
Weaver, Jordan S., Sun, Cheng, Wang, Yongqiang, Kalidindi, Surya R., Doerner, Russ P., Mara, Nathan Allan, and Pathak, Siddhartha. Tue . "Quantifying the mechanical effects of He, W and He + W ion irradiation on tungsten with spherical nanoindentation". United States. https://doi.org/10.1007/s10853-017-1833-8. https://www.osti.gov/servlets/purl/1415419.
@article{osti_1415419,
title = {Quantifying the mechanical effects of He, W and He + W ion irradiation on tungsten with spherical nanoindentation},
author = {Weaver, Jordan S. and Sun, Cheng and Wang, Yongqiang and Kalidindi, Surya R. and Doerner, Russ P. and Mara, Nathan Allan and Pathak, Siddhartha},
abstractNote = {Here, recent advances in spherical nanoindentation protocols have proven very useful for capturing the grain-scale mechanical response of different metals. This is achieved by converting the load–displacement response into an effective indentation stress–strain response which reveals latent information such as the elastic–plastic transition or indentation yield strength and work-hardening behavior and subsequently correlating the response with the material structure (e.g., crystal orientation) at the indentation site. Using these protocols, we systematically study and quantify the microscale mechanical effects of He, W, and He + W ion irradiation on commercially pure, polycrystalline tungsten. The indentation stress–strain response is correlated with the crystal orientation from electron backscatter diffraction, the defect structure from transmission electron microscopy micrographs, and the stopping range of ions in matter calculations of displacement damage and He concentration. He-implanted grains show a much higher indentation yield strength and saturation stress compared to W-ion-irradiated grains for the same displacement damage. There is also good agreement between the dispersed barrier hardening model with a barrier strength of 0.5–0.8 and void models (Bacon–Kochs–Scattergood and Osetsky–Bacon models) with the experimentally observed changes in indentation strength due to the presence of He bubbles. This finding indicates that a high density (~ 9 × 1023 m–3) and concentration (~ 1.5 at.%) of small (~ 1 nm diameter) He bubbles can be moderate to strong barriers to dislocation slip in tungsten.},
doi = {10.1007/s10853-017-1833-8},
journal = {Journal of Materials Science},
number = 7,
volume = 53,
place = {United States},
year = {Tue Dec 19 00:00:00 EST 2017},
month = {Tue Dec 19 00:00:00 EST 2017}
}

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Figures / Tables:

Table 1 Table 1: Indentation strength measurements averaged over near (100), (101), and (111) grains for all indenter sizes and irradiated regions. ΔYind is calculated as the difference between each condition-indenter size and the unirradiated, 100 µm radius indenter yield strength (e.g., ∆𝑌𝑖𝑛𝑑 = 𝑌𝑖𝑛𝑑(𝑊, 1𝜇𝑚, 𝑠𝑎𝑡𝑢𝑟𝑎𝑡𝑖𝑜𝑛) − 𝑌𝑖𝑛𝑑(𝑢𝑛𝑖𝑟𝑟𝑎𝑑𝑖𝑎𝑡𝑒𝑑, 100𝜇𝑚, 0.2% 𝑜𝑓𝑓𝑠𝑒𝑡)more » = 8.23 − 2.97 = 5.26 𝐺𝑃𝑎)« less

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