Strain evaluation using a non-contact deformation measurement system in tensile tests of irradiated F82H and 9cr ODS steels

Journal Article · 28 June 2018 · Nuclear Materials and Energy

DOI: https://doi.org/10.1016/j.nme.2018.06.005 · OSTI ID:1457504

Sakasegawa, Hideo ^[1]; Chen, Xiang  ^[2]; Kato, Taichiro ^[1]; Tanigawa, Hiroyasu ^[1]; Ando, Masami ^[1]; Geringer, Josina Wilna ^[2]; Ukai, Shigeharu ^[3]; Ohtsuka, Satoshi ^[4]

---

1. National Institutes for Quantum and Radiological Science and Technology, Aomori (Japan)
2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
3. Hokkaido Univ., Hokkaido (Japan)
4. Japan Atomic Energy Agency, Ibaraki (Japan)

Here, 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.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• Grant/Contract Number: AC05-00OR22725
• OSTI ID: 1457504
• Alternate ID(s): OSTI ID: 1462890
• Journal Information: Nuclear Materials and Energy, Vol. 16, Issue C; ISSN 2352-1791
• Publisher: ElsevierCopyright Statement
• Country of Publication: United States
• Language: English