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AbstractAbstract
[en] Highlights: • Fe–Cr–Si alloys are considered as a potential ATF fuel cladding coating. • Fe–Cr–Si could offer similar benefits to FeCrAl without as much weld cracking. • Oxidation resistance improves with higher chromium wt. % in Fe–Cr–2Si alloys. • At/above 16 wt % Cr, Fe–Cr–2Si alloys resist corrosion similar to FeCrAl. • Further refinement of Cr and Si could resist oxidation and prevent intermetallics. - Abstract: Fe–Cr–Si alloys are potential candidates as accident tolerant fuel (ATF) cladding, which could offer similar benefits as Fe–Cr–Al alloys. The corrosion and oxidation behaviors of three Fe–Cr–2Si alloys with various chromium content (12 wt. %, 16 wt. %, 20 wt. %) in simulated primary water chemistry of a pressurized water reactor (PWR) were investigated. Post-test characterization included weight change, scanning electron microscopy (SEM), and X-ray Photoelectron Spectroscopy (XPS). The results showed that Fe12Cr2Si had the worst corrosion/oxidation resistance among the three alloys, while Fe16Cr2Si and Fe20Cr2Si showed excellent oxidation resistance due to their thin, continuous, dense oxide layers grown in simulated PWR conditions. These results bring insight into the corrosion behavior of Fe–Cr–Si alloys with varying chromium content exposed to the primary water environment during normal operating conditions found in PWRs.
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S0022311519303290; Available from http://dx.doi.org/10.1016/j.jnucmat.2019.07.035; © 2019 Elsevier B.V. All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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ALLOYS, ALUMINIUM ALLOYS, CHEMICAL REACTIONS, CHEMISTRY, CHROMIUM ALLOYS, DEPOSITION, ELECTRON MICROSCOPY, ELECTRON SPECTROSCOPY, ENERGY SOURCES, ENRICHED URANIUM REACTORS, FUELS, IRON ALLOYS, MATERIALS, MICROSCOPY, NUCLEAR FUELS, PHOTOELECTRON SPECTROSCOPY, POWER REACTORS, REACTOR MATERIALS, REACTORS, SPECTROSCOPY, SURFACE COATING, THERMAL REACTORS, TRANSITION ELEMENT ALLOYS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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