Performance of 14Cr ODS-FeCrAl Cladding Tube for Accident Tolerant Fuel

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Abstract:

In the framework of Accident tolerant fuel (ATF) program, several types of claddings and pellets with enhanced accident tolerance have been developed for light water reactors. Oxide dispersion strengthened (ODS) FeCrAl alloys have been considered as a promising candidate for cladding materials due to their good mechanical strength, excellent structural stability and chemical durability at high temperature. The out-of-pile performance of 14Cr ODS-FeCrAl cladding tube fabricated by cold-rolling, such as microstructure, thermophysical property, mechanical property, and corrosion resistance, has been examined and discussed. The results confirm that iron-based ODS alloy is one of the promising candidates to be used as ATF cladding. It could also aid in the supplement of property database of ODS-FeCrAl for future use in nuclear cladding and structural applications in next generation nuclear systems.

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Periodical:

Materials Science Forum (Volume 1016)

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806-812

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January 2021

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© 2021 Trans Tech Publications Ltd. All Rights Reserved

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[1] B. Raj, Materials science research for sodium cooled fast reactors, Bull. Mater. Sci. 32 (2009) 271-283.

DOI: 10.1007/s12034-009-0041-9

Google Scholar

[2] S. Dryepondt, K.A. Unocic, D.T. Hoelzer, C.P. Massey, and B.A. Pint, Development of low-Cr ODS FeCrAl alloys for accident-tolerant fuel cladding, J. Nucl. Mater. 501 (2018) 59-71.

DOI: 10.1016/j.jnucmat.2017.12.035

Google Scholar

[3] S. Wu, J. Li, W. Li, and S. Liu, Characterization of oxide dispersoids and mechanical properties of 14Cr-ODS-FeCrAl alloys, J. Alloys Compd. 814 (2020) 152282.

DOI: 10.1016/j.jallcom.2019.152282

Google Scholar

[4] J. Li, S. Wu, and S. Liu: submitted to Nuclear power engineering (in Chinese), (2020).

Google Scholar

[5] S.A. Maloy, E. Aydogan, O. Anderoglu, C. Lavender, and Y. Yamamoto, Viability of thin wall tube forming of ATF FeCrAl, Los Alamos National laboratory LA-UR-15-27348, (2016).

DOI: 10.2172/1325688

Google Scholar

[6] L.J. Siefken, E.W. Coryell, E. A. Harvego, and J.K. Hohorst, MATPRO-A Library of Materials Properties for Light-Water-Reactor Accident Analysis, SCDAP/RELAP5/MOD 3.3 Code Manual, (2001).

DOI: 10.2172/100327

Google Scholar

[7] K.A. Terrani, B.A. Pint, Y.J. Kim, K.A. Unocic, Y. Yang, C.M. Silva, H.M. Meyer III, and R.B. Rebak, Uniform corrosion of FeCrAl alloys in LWR coolant environments, J. Nucl. Mater. 479 (2016) 36-47.

DOI: 10.1016/j.jnucmat.2016.06.047

Google Scholar

[8] D.J. Park, H.G. Kim, J.Y. Park, Y.Il Jung, J.H. Park, and Y.H. Koo, A study of the oxidation of FeCrAl alloy in pressurized water and high-temperature steam environment, Corros. Sci. 94 (2015) 459-465.

DOI: 10.1016/j.corsci.2015.02.027

Google Scholar