Material Selection for Accident Tolerant Fuel Cladding
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-H2 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 Ti2AlC form a protective alumina scale in steam. However, commercial Ti2AlC that was not single phase, formed a much thicker oxide at 1200°C in steam and significant TiO2, and therefore Ti2AlC 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.
- Publication Date:
- OSTI Identifier:
- DOE Contract Number:
- Resource Type:
- Resource Relation:
- Conference: TMS Annual 2014, San Diego, CA (United States), 17-20 Feb 2014
- Research Org:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org:
- USDOE Office of Nuclear Energy (NE)
- Country of Publication:
- United States
- 36 MATERIALS SCIENCE; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; ALUMINIUM OXIDES; TITANIUM OXIDES; FUEL CANS; STEAM; OXIDATION; HYDROGEN; COMPARATIVE EVALUATIONS; LOSSES; ACCIDENT-TOLERANT NUCLEAR FUELS; MASS TRANSFER; PHYSICAL RADIATION EFFECTS; MATERIALS; CORROSION RESISTANCE; MOLYBDENUM; IRON BASE ALLOYS; CHROMIUM ALLOYS; ALUMINIUM ALLOYS; TERNARY ALLOY SYSTEMS; TEMPERATURE RANGE 1000-4000 K; TITANIUM CARBIDES; ALUMINIUM CARBIDES LOCA; Mo; FeCrAl; MAX phase; Fuel cladding
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