Abstract
FeCrAl alloys are a leading candidate material for accident tolerant fuel cladding due to their good performance in both normal light-water reactor operating conditions as well as their resilience to high-temperature accident scenarios. For commercial-scale production, new fabrication techniques need to be investigated. In this study, the effects of fabrication methods on the high-temperature steam oxidation performance of C26M (Fe12Cr6Al2Mo in wt.%) were investigated. Three variants of C26M were manufactured: wrought (cast and forged) (WC26M), powder metallurgy hot isostatic pressing (PMC26M), and laser powder bed fusion additive manufacturing (AMC26M). All three variants were exposed to steam at 1200°C for 2 h. Results showed no significant variation in mass change between the variants after steam exposure. All three variants effectively formed stable protective alumina films with ~0.6–1.3 µm thickness. This study suggests FeCrAl alloys have excellent resilience to high-temperature steam in nuclear reactor accident scenarios regardless of the fabrication method.
Highlights
In nuclear power generation, fuel elements release energy incessantly through chain nuclear fission, and they are contained in cladding tubes
additively manufactured C26M (AMC26M) samples were sliced perpendicular to the build direction such that the largest exposed surface area plane was normal to the build direction
Weight gain was between 0.1 mg/cm[2] and 0.2 mg/cm[2]. This weight gain is similar to that observed by others for other Fe12Cr6Al alloys.[14,18]
Summary
Fuel elements release energy incessantly through chain nuclear fission, and they are contained in cladding tubes. High reliability and integrity of cladding tubes should be maintained for the safe operation of nuclear reactors. Zr-based alloys have been widely used as fuel cladding in nuclear reactors for a long time because of their low neutron absorbing cross section, good mechanical properties, and high corrosion resistance in normal operation conditions (light water coolant with operating temperatures in the range of 300°C).[1] in 2011, the Fukushima accident highlighted weakness of standard Zircaloy cladding, including hydrogen production rate, rapid oxidation at elevated temperatures,. FeCrAl alloys have shown outstanding high-temperature (£ 1000°C) oxidation resistance,[13,14,15] remarkable stability of microstructural and mechanical properties at different radiation doses,[16] and high ultimate tensile and yield strength at different temperatures.[17]
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