skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Direct comparison of nanoindentation and tensile test results on reactor-irradiated materials

Abstract

Nanoindentation testing has been used for decades to assess materials on a local scale and to obtain fundamental mechanical property parameters. Nuclear materials research often faces the challenge of testing rather small samples due to the hazardous nature, limited space in reactors, and shallow ion-irradiated zones, fostering the need for small-scale mechanical testing (SSMT). As such, correlating the results from SSMT to bulk properties is particularly of interest. Here, this study compares macroscopic tensile test data (yield and flow stresses) to nanoindentation data (hardness) obtained on a number of different neutron-irradiated materials in order to understand the scaling behavior on radiation-damaged samples.

Authors:
 [1];  [2]; ORCiD logo [3]; ORCiD logo [3];  [2];  [1]
  1. Univ. of California, Berkeley, CA (United States). Nuclear Engineering
  2. Univ. of California, Santa Barbara, CA (United States). Mechanical Engineering
  3. Los Alamos National Lab. (LANL), Los Alamos, NM (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:
1430022
Report Number(s):
LA-UR-18-20299
Journal ID: ISSN 0022-3115; TRN: US1802491
Grant/Contract Number:  
AC52-06NA25396; NE0000639; NU-11-3150; FG03-94ER54275
Resource Type:
Journal Article: Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 504; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; Material Science

Citation Formats

Krumweide, David L, Yamamoto, Takuya, Saleh, Tarik A., Maloy, Stuart Andrew, Odette, G. R., and Hosemann, Peter. Direct comparison of nanoindentation and tensile test results on reactor-irradiated materials. United States: N. p., 2018. Web. doi:10.1016/j.jnucmat.2018.03.021.
Krumweide, David L, Yamamoto, Takuya, Saleh, Tarik A., Maloy, Stuart Andrew, Odette, G. R., & Hosemann, Peter. Direct comparison of nanoindentation and tensile test results on reactor-irradiated materials. United States. doi:10.1016/j.jnucmat.2018.03.021.
Krumweide, David L, Yamamoto, Takuya, Saleh, Tarik A., Maloy, Stuart Andrew, Odette, G. R., and Hosemann, Peter. Tue . "Direct comparison of nanoindentation and tensile test results on reactor-irradiated materials". United States. doi:10.1016/j.jnucmat.2018.03.021.
@article{osti_1430022,
title = {Direct comparison of nanoindentation and tensile test results on reactor-irradiated materials},
author = {Krumweide, David L and Yamamoto, Takuya and Saleh, Tarik A. and Maloy, Stuart Andrew and Odette, G. R. and Hosemann, Peter},
abstractNote = {Nanoindentation testing has been used for decades to assess materials on a local scale and to obtain fundamental mechanical property parameters. Nuclear materials research often faces the challenge of testing rather small samples due to the hazardous nature, limited space in reactors, and shallow ion-irradiated zones, fostering the need for small-scale mechanical testing (SSMT). As such, correlating the results from SSMT to bulk properties is particularly of interest. Here, this study compares macroscopic tensile test data (yield and flow stresses) to nanoindentation data (hardness) obtained on a number of different neutron-irradiated materials in order to understand the scaling behavior on radiation-damaged samples.},
doi = {10.1016/j.jnucmat.2018.03.021},
journal = {Journal of Nuclear Materials},
number = C,
volume = 504,
place = {United States},
year = {Tue Mar 13 00:00:00 EDT 2018},
month = {Tue Mar 13 00:00:00 EDT 2018}
}

Journal Article:
Free Publicly Available Full Text
This content will become publicly available on March 13, 2019
Publisher's Version of Record

Citation Metrics:
Cited by: 2 works
Citation information provided by
Web of Science

Save / Share: