Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding

Dryepondt, Sebastien N.; Unocic, Kinga A.; Hoelzer, David T.; Massey, Caleb P.; Pint, Bruce A.

doi:10.1016/j.jnucmat.2017.12.035

Title: Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding

Journal Article · Wed Jan 10 00:00:00 EST 2018 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2017.12.035· OSTI ID:1461065

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Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Univ. of Tennessee, Knoxville, TN (United States)

Low-Cr oxide dispersion strengthened (ODS) FeCrAl alloys were developed as accident tolerant fuel cladding because of their excellent oxidation resistance at very high temperature, high strength and improved radiation tolerance. Fe-12Cr-5Al wt.% gas atomized powder was ball milled with Y₂O₃+FeO, Y₂O₃+ZrO₂ or Y₂O₃+TiO₂, and the resulting powders were extruded at 950°C. The resulting fine grain structure, particularly for the Ti and Zr containing alloys, led to very high strength but limited ductility. Comparison with variants of commercial PM2000 (Fe-20Cr-5Al) highlighted the significant impact of the powder consolidation step on the alloy grain size and, therefore, on the alloy mechanical properties at T < 500 °C. These low-Cr compositions exhibited good oxidation resistance at 1400 °C in air and steam for 4 h but could not form a protective alumina scale at 1450 °C, similar to observations for fine grained PM2000 alloys. As a result, the effect of alloy grain size, Zr and Ti additions, and impurities on the alloy mechanical and oxidation behaviors are discussed.

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Research Organization:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1461065

Journal Information:: Journal of Nuclear Materials, Vol. 501, Issue C; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 62 works

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