Severe Accident Analysis Of BWR Core Fueled With UO2/FeCrAl with Updated Materials and Melt Properties From Experiments
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Iron-chromium-aluminum (FeCrAl) alloys are being considered as advanced fuel cladding concepts with enhanced accident tolerance. FeCrAl alloys have slower oxidation kinetics and higher strength compared to Zr-based alloys at high temperatures. FeCrAl could be used for fuel cladding and spacer or mixing vane grids in light water reactors and/or as channel box material in boiling water reactors (BWRs). There is a need to assess the potential gains afforded by the FeCrAl accident tolerant fuel concept over the existing zirconium based materials employed today.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1259432
- Report Number(s):
- ORNL/TM-2016/237; AF5810000; NEAF278
- Country of Publication:
- United States
- Language:
- English
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