Nano-indentation measurement of oxide layers formed in LBE on F/M steels

P. Hosemann, Gregory Swadener, J. Welch, N. Li

Research output: Contribution to journalArticle

Abstract

Ferritic/martensitic (F/M) steels (T91, HT-9, EP 823) are candidate materials for future liquid lead or lead bismuth eutectic (LBE) cooled nuclear reactors. To understand the corrosion of these materials in LBE, samples of each material were exposed at 535 °C for 600 h and 200 h at an oxygen content of 10 wt%. After the corrosion tests, the samples were analyzed using SEM, WDX and nano-indentation in cross section. Multi-layered oxide scales were found on the sample surfaces. The compositions of these oxide layers are not entirely in agreement with the literature. The nano-indentation results showed that the E-modulus and hardness of the oxide layers are significantly lower than the values for dense bulk oxide materials. It is assumed that the low values stem from high porosity in the oxide layers. Comparison with in-air oxidized steels show that the E-modulus decreases with increasing oxide layer thickness.
Original languageEnglish
Pages (from-to)201-205
Number of pages5
JournalJournal of Nuclear Materials
Volume377
Issue number1
Early online date6 Mar 2008
DOIs
Publication statusPublished - 30 Jun 2008

Fingerprint

Martensitic steel
Ferritic steel
Nanoindentation
nanoindentation
Bismuth
eutectics
Oxides
Eutectics
bismuth
Lead
steels
oxides
Corrosion
corrosion tests
Steel
nuclear reactors
Nuclear reactors
stems
bismuth lead
corrosion

Keywords

  • reactor
  • steel
  • nanindentation
  • oxidation

Cite this

Hosemann, P. ; Swadener, Gregory ; Welch, J. ; Li, N. / Nano-indentation measurement of oxide layers formed in LBE on F/M steels. In: Journal of Nuclear Materials. 2008 ; Vol. 377, No. 1. pp. 201-205.
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abstract = "Ferritic/martensitic (F/M) steels (T91, HT-9, EP 823) are candidate materials for future liquid lead or lead bismuth eutectic (LBE) cooled nuclear reactors. To understand the corrosion of these materials in LBE, samples of each material were exposed at 535 °C for 600 h and 200 h at an oxygen content of 10 wt{\%}. After the corrosion tests, the samples were analyzed using SEM, WDX and nano-indentation in cross section. Multi-layered oxide scales were found on the sample surfaces. The compositions of these oxide layers are not entirely in agreement with the literature. The nano-indentation results showed that the E-modulus and hardness of the oxide layers are significantly lower than the values for dense bulk oxide materials. It is assumed that the low values stem from high porosity in the oxide layers. Comparison with in-air oxidized steels show that the E-modulus decreases with increasing oxide layer thickness.",
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Nano-indentation measurement of oxide layers formed in LBE on F/M steels. / Hosemann, P.; Swadener, Gregory; Welch, J.; Li, N.

In: Journal of Nuclear Materials, Vol. 377, No. 1, 30.06.2008, p. 201-205.

Research output: Contribution to journalArticle

TY - JOUR

T1 - Nano-indentation measurement of oxide layers formed in LBE on F/M steels

AU - Hosemann, P.

AU - Swadener, Gregory

AU - Welch, J.

AU - Li, N.

N1 - Copyright 2008 Elsevier B.V., All rights reserved.

PY - 2008/6/30

Y1 - 2008/6/30

N2 - Ferritic/martensitic (F/M) steels (T91, HT-9, EP 823) are candidate materials for future liquid lead or lead bismuth eutectic (LBE) cooled nuclear reactors. To understand the corrosion of these materials in LBE, samples of each material were exposed at 535 °C for 600 h and 200 h at an oxygen content of 10 wt%. After the corrosion tests, the samples were analyzed using SEM, WDX and nano-indentation in cross section. Multi-layered oxide scales were found on the sample surfaces. The compositions of these oxide layers are not entirely in agreement with the literature. The nano-indentation results showed that the E-modulus and hardness of the oxide layers are significantly lower than the values for dense bulk oxide materials. It is assumed that the low values stem from high porosity in the oxide layers. Comparison with in-air oxidized steels show that the E-modulus decreases with increasing oxide layer thickness.

AB - Ferritic/martensitic (F/M) steels (T91, HT-9, EP 823) are candidate materials for future liquid lead or lead bismuth eutectic (LBE) cooled nuclear reactors. To understand the corrosion of these materials in LBE, samples of each material were exposed at 535 °C for 600 h and 200 h at an oxygen content of 10 wt%. After the corrosion tests, the samples were analyzed using SEM, WDX and nano-indentation in cross section. Multi-layered oxide scales were found on the sample surfaces. The compositions of these oxide layers are not entirely in agreement with the literature. The nano-indentation results showed that the E-modulus and hardness of the oxide layers are significantly lower than the values for dense bulk oxide materials. It is assumed that the low values stem from high porosity in the oxide layers. Comparison with in-air oxidized steels show that the E-modulus decreases with increasing oxide layer thickness.

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