Direct comparison of nanoindentation and tensile test results on reactor-irradiated materials
Journal Article
·
· Journal of Nuclear Materials
- Univ. of California, Berkeley, CA (United States). Nuclear Engineering
- Univ. of California, Santa Barbara, CA (United States). Mechanical Engineering
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
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.
- Research Organization:
- Los Alamos National Laboratory (LANL)
- Sponsoring Organization:
- USDOE; USDOE Office of Nuclear Energy (NE)
- Grant/Contract Number:
- AC52-06NA25396; FG03-94ER54275; NE0000639
- OSTI ID:
- 1430022
- Alternate ID(s):
- OSTI ID: 1576694
OSTI ID: 22749615
- Report Number(s):
- LA-UR-18-20299
- Journal Information:
- Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: C Vol. 504; ISSN 0022-3115
- Publisher:
- ElsevierCopyright Statement
- Country of Publication:
- United States
- Language:
- English
Strain Gradient Plasticity in Multiprincipal Element Alloys
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journal | August 2019 |
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