Influence of Mechanical Stress at High Temperatures on the Properties of Steels Intended for the Manufacture of Fuel Cladding for Generation IV Reactors

Zbyněk Špirit; Michal Chocholoušek; Marek Šíma

doi:10.4028/www.scientific.net/SSP.270.246

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Influence of Mechanical Stress at High Temperatures on the Properties of Steels Intended for the Manufacture of Fuel Cladding for Generation IV Reactors

Abstract:

This paper describes the testing of thin-walled tubes made of oxide dispersion-hardened steels based on yttrium oxides. Series of mechanical and metallographic tests were carried out on the steels to evaluate the basic material properties. These steels are the candidate materials for the manufacture of the fuel cladding for generation IV nuclear reactors. Mechanical tests were performed on miniature specimens of Fe-9Cr and Fe-14Cr steels at 20 °C, 500 °C, and 625 °C under vacuum. Metallographic, fractographic and EBSD analyses were used to describe microstructure and fracture mechanism of the tested materials.

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Periodical:

Solid State Phenomena (Volume 270)

Pages:

246-252

DOI:

https://doi.org/10.4028/www.scientific.net/SSP.270.246

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Online since:

November 2017

Authors:

Zbyněk Špirit*, Michal Chocholoušek, Marek Šíma

Keywords:

Mechanical Testing at High Temperatures, Microstructure, ODS Steel

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References

[1] P. Yvon, Structural Materials for Generation IV Nuclear Reactors, Woodhead Publishing Series in Energy: Number 106, Duxford, 2017, ISBN: 978-0-08-100912-3 (online).

DOI: 10.1016/b978-0-08-100906-2.09002-9

Google Scholar

[2] Nuclear energy agency organisation for economic co-operation and development http: /www. oecd-nea. org/science/pubs/2015/7268-lead-bismuth-2015. pdf (accessed 7. 10. 2015).

Google Scholar

[3] MATISSE WP4 Summary of first 18 months, [online] http: /www. fp7-matisse. eu, (2014).

Google Scholar

[4] R.L. Klueh et al, Oxide dispersion-strengthened steels: A comparison of some commercial and experimental alloys, Metals and Ceramics Division, Oak Ridge National Laboratory, P.O. Box 2008, MS 6138, Oak Ridge, TN 37831, USA.

DOI: 10.3866/pku.whxb20100414

Google Scholar