Burst and oxidation behavior of Cr-coated Zirlo during simulated LOCA testing
نویسندگان
چکیده
Cr-coated Zr-alloys are a near-term cladding concept to improve reactor safety during accident scenarios. Burst and steam oxidation behavior of bare Zirlo claddings were examined under simulated loss-of-coolant conditions. The 4.4 µm coating had no substantial effect on ballooning or opening geometry but did increase burst temperatures at higher pressures. reduced the compared specimens, in regions high strain, developed through-cracks allowing rapid underlying zirconia formation.
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ژورنال
عنوان ژورنال: Journal of Nuclear Materials
سال: 2022
ISSN: ['1873-4820', '0022-3115']
DOI: https://doi.org/10.1016/j.jnucmat.2022.153679