| About this Abstract |
| Meeting |
2016 TMS Annual Meeting & Exhibition
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| Symposium
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Materials and Fuels for the Current and Advanced Nuclear Reactors V
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| Presentation Title |
Development of ODS FeCrAl Alloys for Accident-tolerant Fuel Cladding |
| Author(s) |
, Caleb Massey, Kinga A Unocic, Dave T Hoelzer, Chad M Parish, Bruce A Pint, Kurt A Terrani |
| On-Site Speaker (Planned) |
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| Abstract Scope |
FeCrAl alloys are prime candidates for accident-tolerant fuel cladding due to their excellent oxidation resistance up to 1450ºC and good mechanical properties at intermediate temperature. Oxide Dispersion Strengthened (ODS) FeCrAl alloys exhibit significantly better tensile strength and are expected to offer superior radiation tolerance than wrought FeCrAls. Several Fe-12-15Cr-5Al ODS alloys where therefore fabricated by ball milling FeCrAl powder with Y2O3 and addition such as TiO2 or ZrO2. The Fe-12Cr-5Al+Y2O3+ZrO2 alloy showed excellent tensile strength and creep resistance up to 800ºC and good oxidation resistance in steam up to 1400ºC. Rolling trials were conducted at 300 and 600ºC to simulate the fabrication of thin tube cladding and a plate thickness ~0.6mm was achieved before the formation of multiple edge cracks. The fabrication and characterization of a second generation of Fe-12-10Cr-5.5-6Al-Zr+Y2O3 ODS alloys with improved ductility will be discussed.
Research sponsored by the U.S. DOE, Office of Nuclear Energy, FCRD Program. |
| Proceedings Inclusion? |
Planned: A print-only volume |