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DOE OSTI · 1224157

Material Selection for Accident Tolerant Fuel Cladding

Pint, Bruce A.·Terrani, Kurt A.·Yamamoto, Yukinori·Snead, Lance Lewis
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Abstract

Alternative cladding materials to Zr-based alloys are being investigated for accident tolerance, which can be defined as > 100X improvement (compared to Zr-based alloys) in oxidation resistance to steam or steam-H 2 environments at ≥ 1200°C for short times. After reviewing a wide range of candidates, current steam oxidation testing is being conducted on Mo, MAX phases and FeCrAl alloys. Recently reported low mass losses for Mo in steam at 800°C could not be reproduced. Both FeCrAl and MAX phase Ti 2 AlC form a protective alumina scale in steam. However, commercial Ti 2 AlC that was not single phase, formed a much thicker oxide at 1200°C in steam and significant TiO 2 , and therefore Ti 2 AlC may be challenging to form as a cladding or a coating. Alloy development for FeCrAl is seeking to maintain its steam oxidation resistance to 1475°C, while reducing its Cr content to minimize susceptibility to irradiation-assisted α´ formation. The composition effects and critical limits to retaining protective scale formation at > 1400°C are still being evaluated.

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11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS36 MATERIALS SCIENCEACCIDENT-TOLERANT NUCLEAR FUELSALUMINIUM ALLOYSALUMINIUM CARBIDESALUMINIUM OXIDESCHROMIUM ALLOYSCOMPARATIVE EVALUATIONSCORROSION RESISTANCEFeCrAlFUEL CANSFuel claddingHYDROGENIRON BASE ALLOYSLOCALOSSESMASS TRANSFERMATERIALSMAX phaseMoMOLYBDENUMOXIDATIONPHYSICAL RADIATION EFFECTSSTEAMTEMPERATURE RANGE 1000-4000 KTERNARY ALLOY SYSTEMSTITANIUM CARBIDESTITANIUM OXIDES

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BibTeXRIS

Pint, Bruce A., Terrani, Kurt A., Yamamoto, Yukinori, Snead, Lance Lewis. 2015-01-01. Material Selection for Accident Tolerant Fuel Cladding. https://www.osti.gov/biblio/1224157

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