Abstract
We developed a non-contact deformation measurement system to accurately evaluate strain for post irradiation tensile testing, since conventional strain gages cannot be used for small size specimens. The strain calculated from cross-head displacement generally includes deformation from specimen shoulders, fixtures, and the test frame in addition to the deformation from the specimen gauge section. In our system, the distance between painted marks within the specimen gauge section was measured using a high resolution video camera to evaluate the specimen deformation during room temperature tensile testing. The test materials were F82H and 9Cr ODS steels irradiated up to ≈71 displacements per atom (dpa) at about 573 K in High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL). Our system yielded accurate stress strain curves without deformations other than the specimen gage section, and the elongation was less than that calculated from cross-head displacement. This system can contribute to expanding the technically reliable database for the design activity of fusion reactor blanket, including the effects of irradiation on tensile properties.
Original language | English |
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Pages (from-to) | 108-113 |
Number of pages | 6 |
Journal | Nuclear Materials and Energy |
Volume | 16 |
DOIs | |
State | Published - Aug 2018 |
Funding
This work is part of the U.S. DOE – QST collaboration on Fusion Materials, sponsored by the U.S. Department of Energy , Office of Fusion Energy Sciences , and National Institutes for Quantum and Radiological Science and Technology under contracts DE-AC05-00OR22725 and NFE-19-02779 , respectively, with UT-Battelle, LLC. A portion of this research used resources at the High Flux Isotope Reactor, a DOE Office of Science User Facility operated by the Oak Ridge National Laboratory.
Funders | Funder number |
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National Institutes for Quantum | |
Radiological Science and Technology | NFE-19-02779 |
U.S. Department of Energy | DE-AC05-00OR22725 |
Fusion Energy Sciences |
Keywords
- Oxide dispersion strengthened steel
- Post irradiation experiment
- Reduced activation ferritic/martensitic steel
- Small specimen technology
- Strain
- Tensile test