About this Abstract |
Meeting |
2022 TMS Annual Meeting & Exhibition
|
Symposium
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Materials Systems for the Future of Fusion Energy
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Presentation Title |
NOW ON-DEMAND ONLY - Low Temperature Hardening-embrittlement in Neutron Irradiated ODS Steels |
Author(s) |
Arunodaya Bhattacharya, Samara M Levine, Xiang Chen, Takashi Nozawa, Steven J Zinkle, Yutai Katoh |
On-Site Speaker (Planned) |
Arunodaya Bhattacharya |
Abstract Scope |
A major challenge for the fusion reactor first-wall/blanket is the well-known issue of irradiation-induced low temperature hardening-embrittlement (LTHE) of structural steels, resulting in loss of fracture toughness. While LTHE in RAFM steels significantly improves for irradiation temperatures ≥ 350 °C, the susceptibility of ODS steels to LTHE is not well-evaluated. Using post-irradiation mechanical property testing, we reveal compelling evidence of LTHE in various ODS steels after neutron irradiations in the high flux isotope reactor between 300-500 °C and doses up to ~20 dpa. The LTHE scenario in ODS is compared with RAFM steels to identify and rationalize potential design challenges such emerging results may pose. Research sponsored the U.S. Department of Energy, Office of Fusion Energy Sciences under contact DE-AC05-00OR22725 with UT-Battelle LLC. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Iron and Steel, Mechanical Properties |