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

Yamamoto, Yukinori; Pint, Bruce A.; Terrani, Kurt A.; Field, Kevin G.; Yang, Ying; Snead, Lance Lewis

doi:10.1016/j.jnucmat.2015.10.019

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

Journal Article · Mon Oct 19 00:00:00 EDT 2015 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2015.10.019· OSTI ID:1324043

Yamamoto, Yukinori ^[1]; Pint, Bruce A. ^[1]; Terrani, Kurt A. ^[1]; Field, Kevin G. ^[1]; Yang, Ying ^[1]; Snead, Lance Lewis ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

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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Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Center for Nanophase Materials Sciences (CNMS)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE), Fuel Cycle Technologies (NE-5); USDOE Office of Nuclear Energy (NE), Nuclear Fuel Cycle and Supply Chain; USDOE Office of Science (SC), Basic Energy Sciences (BES)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1324043

Alternate ID(s):: OSTI ID: 1459743

Journal Information:: Journal of Nuclear Materials, Vol. 467, Issue P2; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 249 works

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References (32)

Current knowledge on core degradation phenomena, a review Hofmann, P. Journal of Nuclear Materials, Vol. 270, Issue 1-2 https://doi.org/10.1016/S0022-3115(98)00899-X	journal	April 1999
Oxidation of Zircaloy by steam Moalem, M.; Olander, D. R. Journal of Nuclear Materials, Vol. 182 https://doi.org/10.1016/0022-3115(91)90428-A	journal	May 1991
Synopsis and outcome of the QUENCH experimental program Steinbrück, M.; Große, M.; Sepold, L. Nuclear Engineering and Design, Vol. 240, Issue 7 https://doi.org/10.1016/j.nucengdes.2010.03.021	journal	July 2010
Advanced oxidation-resistant iron-based alloys for LWR fuel cladding Terrani, K. A.; Zinkle, S. J.; Snead, L. L. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.06.041	journal	May 2014
Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions Ott, L. J.; Robb, K. R.; Wang, D. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.09.052	journal	May 2014
Accident tolerant fuels for LWRs: A perspective Zinkle, S. J.; Terrani, K. A.; Gehin, J. C. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.12.005	journal	May 2014
Oxidation Studies on the Iron-Chromium-Aluminum Heater Alloys Gulbransen, Earl A.; Andrew, Kenneth F. Journal of The Electrochemical Society, Vol. 106, Issue 4 https://doi.org/10.1149/1.2427333	journal	January 1959
High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments Pint, B. A.; Terrani, K. A.; Brady, M. P. Journal of Nuclear Materials, Vol. 440, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.05.047	journal	September 2013
Oxidation of fuel cladding candidate materials in steam environments at high temperature and pressure Cheng, Ting; Keiser, James R.; Brady, Michael P. Journal of Nuclear Materials, Vol. 427, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.05.007	journal	August 2012
Development of ODS FeCrAl for Compatibility in Fusion and Fission Energy Applications Pint, B. A.; Dryepondt, S.; Unocic, K. A. JOM, Vol. 66, Issue 12 https://doi.org/10.1007/s11837-014-1200-z	journal	November 2014
Effect of steam on high temperature oxidation behaviour of alumina-forming alloys Pint, B. A.; Unocic, K. A.; Terrani, K. A. Materials at High Temperatures, Vol. 32, Issue 1-2 https://doi.org/10.1179/0960340914Z.00000000058	journal	January 2015
Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors George, Nathan Michael; Terrani, Kurt; Powers, Jeff Annals of Nuclear Energy, Vol. 75 https://doi.org/10.1016/j.anucene.2014.09.005	journal	January 2015
Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions Wu, Xu; Kozlowski, Tomasz; Hales, Jason D. Annals of Nuclear Energy, Vol. 85 https://doi.org/10.1016/j.anucene.2015.06.032	journal	November 2015
Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys Field, Kevin G.; Hu, Xunxiang; Littrell, Kenneth C. Journal of Nuclear Materials, Vol. 465 https://doi.org/10.1016/j.jnucmat.2015.06.023	journal	October 2015
The influence of alloying elements on the development and maintenance of protective scales Stott, F. H.; Wood, G. C.; Stringer, J. Oxidation of Metals, Vol. 44, Issue 1-2 https://doi.org/10.1007/BF01046725	journal	August 1995
The effect of alloying on 485°C embrittlement Courtnall, M.; Pickering, F. B. Metal Science, Vol. 10, Issue 8 https://doi.org/10.1179/030634576790432353	journal	August 1976
The 885° f (475° c) embrittlement of ferritic stainless steels Grobner, P. J. Metallurgical Transactions, Vol. 4, Issue 1 https://doi.org/10.1007/BF02649625	journal	January 1973
A SANS investigation of the irradiation-enhanced α–α′ phases separation in 7–12 Cr martensitic steels Mathon, M. H.; de Carlan, Y.; Geoffroy, G. Journal of Nuclear Materials, Vol. 312, Issue 2-3 https://doi.org/10.1016/S0022-3115(02)01630-6	journal	February 2003
Mapping of 475°C embrittlement in ferritic Fe–Cr–Al alloys Kobayashi, Satoru; Takasugi, Takayuki Scripta Materialia, Vol. 63, Issue 11 https://doi.org/10.1016/j.scriptamat.2010.08.015	journal	November 2010
Microstructural stability of Fe–Cr–Al alloys at 450–550 °C Ejenstam, Jesper; Thuvander, Mattias; Olsson, Pär Journal of Nuclear Materials, Vol. 457 https://doi.org/10.1016/j.jnucmat.2014.11.101	journal	February 2015
The effect of Al on the 475°C embrittlement of Fe–Cr alloys Li, Wei; Lu, Song; Hu, Qing-Miao Computational Materials Science, Vol. 74 https://doi.org/10.1016/j.commatsci.2013.03.021	journal	June 2013
The effect of heat treatment on recrystallized microstructure, precipitation and ductility of hot-rolled Fe–Cr–Al–REM ferritic stainless steel sheets Qu, H. P.; Lang, Y. P.; Yao, C. F. Materials Science and Engineering: A, Vol. 562 https://doi.org/10.1016/j.msea.2012.11.008	journal	February 2013
Optimization of Reactive-Element Additions to Improve Oxidation Performance of Alumina-Forming Alloys Pint, Bruce A. Journal of the American Ceramic Society, Vol. 86, Issue 4 https://doi.org/10.1111/j.1151-2916.2003.tb03358.x	journal	April 2003
Experimental observations in support of the dynamic-segregation theory to explain the reactive-element effect Pint, B. A. Oxidation of Metals, Vol. 45, Issue 1-2 https://doi.org/10.1007/BF01046818	journal	February 1996
The influence of yttrium additions on the oxide-scale adhesion to an iron-chromium-aluminum alloy Golightly, F. A.; Stott, F. H.; Wood, G. C. Oxidation of Metals, Vol. 10, Issue 3 https://doi.org/10.1007/BF00612158	journal	June 1976
The mechanism of oxide film formation on austenitic stainless steels in high temperature water Stellwag, B. Corrosion Science, Vol. 40, Issue 2-3 https://doi.org/10.1016/S0010-938X(97)00140-6	journal	February 1998
PANDAT software with PanEngine, PanOptimizer and PanPrecipitation for multi-component phase diagram calculation and materials property simulation Cao, W.; Chen, S. -L.; Zhang, F. Calphad, Vol. 33, Issue 2 https://doi.org/10.1016/j.calphad.2008.08.004	journal	June 2009
Thermodynamic modeling and kinetics simulation of precipitate phases in AISI 316 stainless steels Yang, Y.; Busby, J. T. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.02.008	journal	May 2014
Elevated temperature ferritic and martensitic steels and their application to future nuclear reactors Klueh, R. L. International Materials Reviews, Vol. 50, Issue 5 https://doi.org/10.1179/174328005X41140	journal	October 2005
Ferritic/martensitic steels for next-generation reactors Klueh, R. L.; Nelson, A. T. Journal of Nuclear Materials, Vol. 371, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2007.05.005	journal	September 2007
Deformation behavior of laser welds in high temperature oxidation resistant Fe–Cr–Al alloys for fuel cladding applications Field, Kevin G.; Gussev, Maxim N.; Yamamoto, Yukinori Journal of Nuclear Materials, Vol. 454, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.08.013	journal	November 2014
On the delamination of FeCrAl ODS alloys Chao, J.; Capdevila-Montes, C.; González-Carrasco, J. L. Materials Science and Engineering: A, Vol. 515, Issue 1-2 https://doi.org/10.1016/j.msea.2009.03.017	journal	July 2009

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Oxidation Characteristics of Two FeCrAl Alloys in Air and Steam from 800°C to 1300°C Rebak, Raul B.; Gupta, Vipul K.; Larsen, Michael JOM, Vol. 70, Issue 8 https://doi.org/10.1007/s11837-018-2979-9	journal	June 2018
Reactive Element Effects in High-Temperature Alloys Disentangled Babic, Vedad; Geers, Christine; Panas, Itai Oxidation of Metals, Vol. 93, Issue 1-2 https://doi.org/10.1007/s11085-019-09946-6	journal	November 2019
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