Severe Accident Analysis Of BWR Core Fueled With UO₂/FeCrAl with Updated Materials and Melt Properties From Experiments

Technical Report · Wed Jun 01 00:00:00 EDT 2016

DOI:https://doi.org/10.2172/1259432· OSTI ID:1259432

Robb, Kevin R. ^[1]; McMurray, Jake W. ^[1]; Terrani, Kurt A. ^[1]

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1. 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