Advancements in FeCrAl Alloys for Enhanced Accident Tolerant Fuel Cladding for Light Water Reactors

Journal Article · Wed Jun 15 04:00:00 EDT 2016 · Transactions of the American Nuclear Society

OSTI ID:22992053

Field, Kevin G.; Yamamoto, Yukinori; Gussev, Maxim N.; Unocic, Kinga A.; Pint, Bruce A.; Terrani, Kurt A. ^[1]; Brigg, Samuel A. ^[2]; Rebak, Raul B. ^[3]; Snead, Lance L. ^[4]

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1. Oak Ridge National Laboratory - ORNL, Oak Ridge, TN 37831 (United States)
2. Univesity of Wisconsin - Madison, Madison, WI 53703 (United States)
3. GE Global Research, Schenectady, NY 12309 (United States)
4. Massachusetts Institute of Technology, Cambridge, MA 02139 (United States)

Advanced FeCrAl alloys are being considered as an enhanced accident tolerant fuel (ATF) cladding for light water reactor (LWR) applications as they can exhibit slower reaction kinetics with high temperature steam and have a reduced production of hydrogen during accident scenarios compared both to historic 304L cladding and Zircaloy. Both of these attributes are key towards producing a fuel-form with enhanced accident tolerance over the current Zr-based-UO{sub 2} fuel form in deployment. A multi-year, multi-laboratory effort has been established to rapidly advance FeCrAl alloys as an ATF concept. This effort has focused on optimizing the microstructure and composition of these alloys in an attempt to provide performance on-par with or better than the current Zr-based cladding in both normal operating conditions and under accident scenarios. To date, a significant database supporting key performance factors in both scenarios has been developed. Based on this database, a compositional and microstructural window has been identified providing the insight for an optimized, advanced nuclear-grade FeCrAl alloy for LWRs. This work will provide a comprehensive overview of the systematic effort to advance FeCrAl alloys as an enhanced ATF cladding in commercial LWRs. Efforts undertaken by this multi-year, multi-laboratory program have shown the viability of using FeCrAl alloys as an ATF cladding in LWRs. Most importantly, it has been shown the oxidation resistance, decreased hydrogen production, and reduced heat generation of FeCrAl alloys strongly contribute to its ATF capability. Furthermore, it has been shown that the normal operational performance of a FeCrAl cladding can rival that of Zr-based alloys. Finally, it was found that optimizing the performance of FeCrAl cladding materials requires balancing the starting composition and microstructure in order to satisfy key performance indicators such as oxidation resistance and radiation tolerance. (authors)

• OSTI ID: 22992053
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Journal Issue: 1 Vol. 114; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
ACCIDENT-TOLERANT NUCLEAR FUELS
ACCIDENTS
CLADDING
MICROSTRUCTURE
OPTIMIZATION
OXIDATION
PERFORMANCE
REACTION KINETICS
TOLERANCE
URANIUM DIOXIDE
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY