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Title: Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors

Abstract

Ion irradiation is often used to simulate the effects of neutron irradiation due to reduced activation of materials and vastly increased dose rates. However, the low penetration depth of ions requires the development of small-scale mechanical testing techniques, such as nanoindentation and microcompression, in order to measure mechanical properties of the irradiated material. In this study, several candidate structural alloys for Gen-IV reactors (800H, T91, nanocrystalline T91 and 14YWT) were irradiated with 70 MeV Fe 9+ ions at 452 °C to an average damage of 20.68 dpa. Both the nanoindentation and microcompression techniques revealed significant irradiation hardening and an increase in yield stress after irradiation in austenitic 800H and ferritic-martensitic T91 alloys. Ion irradiation was observed to have minimal effect on the mechanical properties of nanocrystalline T91 and oxide dispersion strengthened 14YWT. These observations are further supported by line broadening analysis of X-ray diffraction measurements, which show a significantly smaller increase in dislocation density in the 14YWT and nanocrystalline T91 alloys after irradiation. In addition, good agreement was observed between cross-sectional nanoindentation and the damage profile from SRIM calculations.

Authors:
 [1];  [2]; ORCiD logo [3]; ORCiD logo [2];  [4];  [5];  [6];  [5]; ORCiD logo [4];  [7];  [8];  [9];  [2]
  1. Univ. of California, Berkeley, CA (United States). Dept. of Materials Science and Engineering
  2. Univ. of California, Berkeley, CA (United States). Dept. of Nuclear Engineering
  3. Univ. of Oxford (United Kingdom). Dept. of Materials
  4. Univ. of Manchester (United Kingdom). Materials Performance Center
  5. Eötvös Loránd Univ. Budapest, Budapest (Hungary). Dept. of Materials Physics
  6. Univ. of Manchester (United Kingdom). Materials Performance Center; Eötvös Loránd Univ. Budapest, Budapest (Hungary). Dept. of Materials Physics
  7. Queen's Univ., Kingston, ON (Canada). Dept. of Mechanical and Materials Engineering
  8. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States). Center of Accelerator Mass Spectrometry
  9. Univ. of California, Berkeley, CA (United States). Dept. of Materials Science and Engineering; Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States). National Center for Electron Microscopy, Molecular Foundry
Publication Date:
Research Org.:
Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)
Sponsoring Org.:
USDOE Office of Science (SC), Basic Energy Sciences (BES) (SC-22)
OSTI Identifier:
1454876
Alternate Identifier(s):
OSTI ID: 1493260
Grant/Contract Number:  
AC02-05CH11231
Resource Type:
Published Article
Journal Name:
Nuclear Materials and Energy
Additional Journal Information:
Journal Volume: 16; Journal Issue: C; Journal ID: ISSN 2352-1791
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE

Citation Formats

Prasitthipayong, A., Frazer, D., Kareer, A., Abad, M. D., Garner, A., Joni, B., Ungar, T., Ribarik, G., Preuss, M., Balogh, L., Tumey, S. J., Minor, A. M., and Hosemann, P. Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors. United States: N. p., 2018. Web. doi:10.1016/j.nme.2018.05.018.
Prasitthipayong, A., Frazer, D., Kareer, A., Abad, M. D., Garner, A., Joni, B., Ungar, T., Ribarik, G., Preuss, M., Balogh, L., Tumey, S. J., Minor, A. M., & Hosemann, P. Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors. United States. doi:10.1016/j.nme.2018.05.018.
Prasitthipayong, A., Frazer, D., Kareer, A., Abad, M. D., Garner, A., Joni, B., Ungar, T., Ribarik, G., Preuss, M., Balogh, L., Tumey, S. J., Minor, A. M., and Hosemann, P. Tue . "Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors". United States. doi:10.1016/j.nme.2018.05.018.
@article{osti_1454876,
title = {Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors},
author = {Prasitthipayong, A. and Frazer, D. and Kareer, A. and Abad, M. D. and Garner, A. and Joni, B. and Ungar, T. and Ribarik, G. and Preuss, M. and Balogh, L. and Tumey, S. J. and Minor, A. M. and Hosemann, P.},
abstractNote = {Ion irradiation is often used to simulate the effects of neutron irradiation due to reduced activation of materials and vastly increased dose rates. However, the low penetration depth of ions requires the development of small-scale mechanical testing techniques, such as nanoindentation and microcompression, in order to measure mechanical properties of the irradiated material. In this study, several candidate structural alloys for Gen-IV reactors (800H, T91, nanocrystalline T91 and 14YWT) were irradiated with 70 MeV Fe9+ ions at 452 °C to an average damage of 20.68 dpa. Both the nanoindentation and microcompression techniques revealed significant irradiation hardening and an increase in yield stress after irradiation in austenitic 800H and ferritic-martensitic T91 alloys. Ion irradiation was observed to have minimal effect on the mechanical properties of nanocrystalline T91 and oxide dispersion strengthened 14YWT. These observations are further supported by line broadening analysis of X-ray diffraction measurements, which show a significantly smaller increase in dislocation density in the 14YWT and nanocrystalline T91 alloys after irradiation. In addition, good agreement was observed between cross-sectional nanoindentation and the damage profile from SRIM calculations.},
doi = {10.1016/j.nme.2018.05.018},
journal = {Nuclear Materials and Energy},
number = C,
volume = 16,
place = {United States},
year = {2018},
month = {6}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record
DOI: 10.1016/j.nme.2018.05.018

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