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Improving Nuclear Power Plant Safety with FeCrAl Alloy Fuel Cladding

Published online by Cambridge University Press:  09 January 2017

Raul B. Rebak,
Kurt A. Terrani,
William P. Gassmann,
John B. Williams and
Kevin L. Ledford
Raul B. Rebak*
Affiliation:
GE Global Research, 1 Research Circle, CEB2551, Schenectady, NY 12309, U.S.A.
Kurt A. Terrani
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN 37831
William P. Gassmann
Affiliation:
Exelon Generation, Kennett Square, PA 19348
John B. Williams
Affiliation:
Southern Nuclear, Chelsea, AL 35043
Kevin L. Ledford
Affiliation:
Global Nuclear Fuels Americas, Wilmington NC 28401
*
*(Email: rebak@ge.com)

Abstract

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The US Department of Energy (DOE) is partnering with fuel vendors to develop enhanced accident tolerant nuclear fuels for Generation III water cooled reactors. In comparison with the standard current uranium dioxide and zirconium alloy system UO2-Zr), the proposed alternative accident tolerant fuel (ATF) should better tolerate loss of cooling in the core for a considerably longer time while maintaining or improving the fuel performance during normal operation conditions. General Electric, Oak Ridge National Laboratory and their partners have proposed to replace zirconium based alloy cladding in current commercial power reactors with an iron-chromium-aluminum (FeCrAl) alloy cladding such as APMT. The use of FeCrAl alloys will greatly reduce the risk of operating the power reactors to produce electricity.

Keywords

corrosionenergy generationnuclear materials

Information

Type
Articles
Information
MRS Advances , Volume 2 , Issue 21-22: Energy and Sustainability , 2017, pp. 1217 - 1224
Copyright
Copyright © Materials Research Society 2017 

References

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