Abstract
The sectored flexural specimen was developed over a decade ago to measure the strength of ceramic and glass tubes and cylinders in which flaws on a tube's or cylinder's outer surface are limiters of axial tensile failure stress. Using the specimen's geometry, the associated axial tensile failure stress can be analytically calculated from the failure force measured from simple uniaxial bending, and multiple specimens (and test data) can be harvested from a single tube or cylinder. The sector angles of specimens in previous studies were somewhat arbitrarily chosen and usually produced validly occurring fractures and data; however, if the angle used was too small (relative to the tube's or cylinder's geometry), then undesirable application-irrelevant edge-located failures resulted. To avoid such failures in specimen design, a threshold sector angle was identified to guide the selection of a minimum sector angle (and consequential cross section) for any arbitrary sector flexural specimen harvested from a tube or cylinder. If the sector angle of the specimen is larger than the threshold value, then fracture will not occur at a specimen's edge and the measured axial failure stress will be limited by surface-located flaws on the tube's or cylinder's outer surface.
| Original language | English |
|---|---|
| Pages (from-to) | 367-377 |
| Number of pages | 11 |
| Journal | International Journal of Applied Ceramic Technology |
| Volume | 16 |
| Issue number | 1 |
| DOIs | |
| State | Published - Jan 1 2019 |
Funding
Research sponsored by the Office of Advanced Reactor Technologies Program, DOE Office of Nuclear Energy, under contract DE‐AC05‐00OR22725 with UT‐Battelle, LLC. The authors thank ORNL's Y. Katoh for financial and programmatic support and D. Stringfield for assisting with the fixture fabrication. Lastly, ORNL's D. Stevens, J.‐Y. Wang, H. Jiang, and E. Lara‐Curzio, and the US Army Research Laboratory's J. Swab are thanked for their reviews and helpful input. Funding information USDOE Office of Nuclear Energy. Research sponsored by the Office of Advanced Reactor Technologies Program, DOE Office of Nuclear Energy, under contract DE-AC05-00OR22725 with UT-Battelle, LLC. The authors thank ORNL's Y. Katoh for financial and programmatic support and D. Stringfield for assisting with the fixture fabrication. Lastly, ORNL's D. Stevens, J.-Y. Wang, H. Jiang, and E. Lara-Curzio, and the US Army Research Laboratory's J. Swab are thanked for their reviews and helpful input. *This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan).
| Funders | Funder number |
|---|---|
| DOE Office of Nuclear Energy | DE-AC05-00OR22725 |
| Office of Advanced Reactor Technologies Program | |
| USDOE Office of Nuclear Energy | |
| U.S. Department of Energy | |
| Office of Nuclear Energy | DE‐AC05‐00OR22725 |
| Oak Ridge National Laboratory | |
| Army Research Laboratory |
Keywords
- brittle materials
- failure
- strength