Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors

Y. Yamamoto; B. A. Pint; K. A. Terrani; K. G. Field; Y. Yang; L. L. Snead

doi:10.1016/j.jnucmat.2015.10.019

Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors

Y. Yamamoto, B. A. Pint, K. A. Terrani, K. G. Field, Y. Yang, L. L. Snead

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Abstract

Development of nuclear grade, iron-based wrought FeCrAl alloys has been initiated for light water reactor (LWR) fuel cladding to serve as a substitute for zirconium-based alloys with enhanced accident tolerance. Ferritic alloys with sufficient chromium and aluminum additions can exhibit significantly improved oxidation kinetics in high-temperature steam environments when compared to zirconium-based alloys. In the first phase, a set of model FeCrAl alloys containing 10-20Cr, 3-5Al, and 0-0.12Y in weight percent, were prepared by conventional arc-melting and hot-working processes to explore the effect of composition on the properties of FeCrAlY alloys. It was found that the tensile properties were insensitive to the alloy compositions studied; however, the steam oxidation resistance strongly depended on both the chromium and the aluminum contents. The second phase development focused on strengthening Fe-13Cr-5Al with minor alloying additions of molybdenum, niobium, and silicon. Combined with an optimized thermo-mechanical treatment, a thermally stable microstructure was produced with improved tensile properties at temperatures up to 741°C.

Original language	English
Pages (from-to)	703-716
Number of pages	14
Journal	Journal of Nuclear Materials
Volume	467
DOIs	https://doi.org/10.1016/j.jnucmat.2015.10.019
State	Published - Dec 2015

Funding

This manuscript has been authored by UT-Battelle, LLC under Contract No. DE-AC05-00OR22725 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan ( http://energy.gov/downloads/doe-public-access-plan ). Authors would like to acknowledge D. Harper, G. Cox, J. Mayotte, T. Geer, E. Manneschmidt, and A. Zinkle for their technical support, and D. Hoelzer and S. Dryepondt for their fruitful discussions. This research was funded by the U.S. Department of Energy's Office of Nuclear Energy, Advanced Fuel Campaign of the Fuel Cycle R&D program . ORNL's Center for Nanophase Materials Sciences, CNMS, which is sponsored by the Scientific User Facilities Division, Office of Basic Energy Sciences, U.S. Department of Energy , is also acknowledged.

Keywords

Accident tolerant fuel cladding
FeCrAl
LWR
Nuclear grade
Wrought

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10.1016/j.jnucmat.2015.10.019

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title = "Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors",

abstract = "Development of nuclear grade, iron-based wrought FeCrAl alloys has been initiated for light water reactor (LWR) fuel cladding to serve as a substitute for zirconium-based alloys with enhanced accident tolerance. Ferritic alloys with sufficient chromium and aluminum additions can exhibit significantly improved oxidation kinetics in high-temperature steam environments when compared to zirconium-based alloys. In the first phase, a set of model FeCrAl alloys containing 10-20Cr, 3-5Al, and 0-0.12Y in weight percent, were prepared by conventional arc-melting and hot-working processes to explore the effect of composition on the properties of FeCrAlY alloys. It was found that the tensile properties were insensitive to the alloy compositions studied; however, the steam oxidation resistance strongly depended on both the chromium and the aluminum contents. The second phase development focused on strengthening Fe-13Cr-5Al with minor alloying additions of molybdenum, niobium, and silicon. Combined with an optimized thermo-mechanical treatment, a thermally stable microstructure was produced with improved tensile properties at temperatures up to 741°C.",

keywords = "Accident tolerant fuel cladding, FeCrAl, LWR, Nuclear grade, Wrought",

author = "Y. Yamamoto and Pint, {B. A.} and Terrani, {K. A.} and Field, {K. G.} and Y. Yang and Snead, {L. L.}",

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doi = "10.1016/j.jnucmat.2015.10.019",

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AU - Yamamoto, Y.

AU - Pint, B. A.

AU - Terrani, K. A.

AU - Field, K. G.

AU - Yang, Y.

AU - Snead, L. L.

PY - 2015/12

Y1 - 2015/12

N2 - Development of nuclear grade, iron-based wrought FeCrAl alloys has been initiated for light water reactor (LWR) fuel cladding to serve as a substitute for zirconium-based alloys with enhanced accident tolerance. Ferritic alloys with sufficient chromium and aluminum additions can exhibit significantly improved oxidation kinetics in high-temperature steam environments when compared to zirconium-based alloys. In the first phase, a set of model FeCrAl alloys containing 10-20Cr, 3-5Al, and 0-0.12Y in weight percent, were prepared by conventional arc-melting and hot-working processes to explore the effect of composition on the properties of FeCrAlY alloys. It was found that the tensile properties were insensitive to the alloy compositions studied; however, the steam oxidation resistance strongly depended on both the chromium and the aluminum contents. The second phase development focused on strengthening Fe-13Cr-5Al with minor alloying additions of molybdenum, niobium, and silicon. Combined with an optimized thermo-mechanical treatment, a thermally stable microstructure was produced with improved tensile properties at temperatures up to 741°C.

AB - Development of nuclear grade, iron-based wrought FeCrAl alloys has been initiated for light water reactor (LWR) fuel cladding to serve as a substitute for zirconium-based alloys with enhanced accident tolerance. Ferritic alloys with sufficient chromium and aluminum additions can exhibit significantly improved oxidation kinetics in high-temperature steam environments when compared to zirconium-based alloys. In the first phase, a set of model FeCrAl alloys containing 10-20Cr, 3-5Al, and 0-0.12Y in weight percent, were prepared by conventional arc-melting and hot-working processes to explore the effect of composition on the properties of FeCrAlY alloys. It was found that the tensile properties were insensitive to the alloy compositions studied; however, the steam oxidation resistance strongly depended on both the chromium and the aluminum contents. The second phase development focused on strengthening Fe-13Cr-5Al with minor alloying additions of molybdenum, niobium, and silicon. Combined with an optimized thermo-mechanical treatment, a thermally stable microstructure was produced with improved tensile properties at temperatures up to 741°C.

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KW - Wrought

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ER -

Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors

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