Steam oxidation behavior of FeCrAl cladding

B. A. Pint; K. A. Terrani; R. B. Rebak

doi:10.1007/978-3-319-68454-3_20

Steam oxidation behavior of FeCrAl cladding

B. A. Pint, K. A. Terrani, R. B. Rebak

Materials Science and Technology Div

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

10 Scopus citations

Abstract

In order to better understand the high temperature steam oxidation behavior of FeCrAl alloys, this study addressed two topics. The first is continuing to evaluate the effect of alloy composition on performance of commercial and laboratory-made candidate FeCrAl alloys. For a few optimized compositions, this includes the performance of commercially-made tubing where it is clear that dropping the Cr content from 20% to 10–13% reduces the maximum operating temperature in steam by ~50 °C. The second addresses more realistic accident conditions. Model FeCrAl compositions that were exposed in ~300 °C water for 1 year were subsequently “ramp” tested in steam at 5 °C/min to 1500 °C to assess the effect of the Fe-rich oxide formed in water on the subsequent steam oxidation resistance. For Fe-18Cr-3Al+Y, the 1 year exposures in three different LWR water chemistries did not affect the ability to form alumina to 1500 °C. However, for marginal alloys Fe-13Cr-4Al and Fe-10Cr-5Al, some specimens began forming voluminous Fe-rich oxide at lower temperatures.

Original language	English
Title of host publication	Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
Editors	Michael Wright, Denise Paraventi, John H. Jackson
Publisher	Springer International Publishing
Pages	235-244
Number of pages	10
ISBN (Print)	9783319684536
DOIs	https://doi.org/10.1007/978-3-319-68454-3_20
State	Published - 2018
Event	18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017 - Portland, United States Duration: Aug 13 2017 → Aug 17 2017

Publication series

Name	Minerals, Metals and Materials Series
Volume	Part F11
ISSN (Print)	2367-1181
ISSN (Electronic)	2367-1696

Conference

Conference	18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017
Country/Territory	United States
City	Portland
Period	08/13/17 → 08/17/17

Funding

Notice: 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).

Keywords

AlO
FeCrAl
Fuel cladding
High temperature oxidation
Steam

Access to Document

10.1007/978-3-319-68454-3_20

Cite this

Pint, B. A., Terrani, K. A., & Rebak, R. B. (2018). Steam oxidation behavior of FeCrAl cladding. In M. Wright, D. Paraventi, & J. H. Jackson (Eds.), Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors (pp. 235-244). (Minerals, Metals and Materials Series; Vol. Part F11). Springer International Publishing. https://doi.org/10.1007/978-3-319-68454-3_20

Pint, B. A. ; Terrani, K. A. ; Rebak, R. B. / Steam oxidation behavior of FeCrAl cladding. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. editor / Michael Wright ; Denise Paraventi ; John H. Jackson. Springer International Publishing, 2018. pp. 235-244 (Minerals, Metals and Materials Series).

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title = "Steam oxidation behavior of FeCrAl cladding",

abstract = "In order to better understand the high temperature steam oxidation behavior of FeCrAl alloys, this study addressed two topics. The first is continuing to evaluate the effect of alloy composition on performance of commercial and laboratory-made candidate FeCrAl alloys. For a few optimized compositions, this includes the performance of commercially-made tubing where it is clear that dropping the Cr content from 20% to 10–13% reduces the maximum operating temperature in steam by ~50 °C. The second addresses more realistic accident conditions. Model FeCrAl compositions that were exposed in ~300 °C water for 1 year were subsequently “ramp” tested in steam at 5 °C/min to 1500 °C to assess the effect of the Fe-rich oxide formed in water on the subsequent steam oxidation resistance. For Fe-18Cr-3Al+Y, the 1 year exposures in three different LWR water chemistries did not affect the ability to form alumina to 1500 °C. However, for marginal alloys Fe-13Cr-4Al and Fe-10Cr-5Al, some specimens began forming voluminous Fe-rich oxide at lower temperatures.",

keywords = "AlO, FeCrAl, Fuel cladding, High temperature oxidation, Steam",

author = "Pint, {B. A.} and Terrani, {K. A.} and Rebak, {R. B.}",

note = "Publisher Copyright: {\textcopyright} The Minerals, Metals & Materials Society 2018.; 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017 ; Conference date: 13-08-2017 Through 17-08-2017",

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doi = "10.1007/978-3-319-68454-3_20",

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Pint, BA, Terrani, KA & Rebak, RB 2018, Steam oxidation behavior of FeCrAl cladding. in M Wright, D Paraventi & JH Jackson (eds), Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Minerals, Metals and Materials Series, vol. Part F11, Springer International Publishing, pp. 235-244, 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017, Portland, United States, 08/13/17. https://doi.org/10.1007/978-3-319-68454-3_20

Steam oxidation behavior of FeCrAl cladding. / Pint, B. A.; Terrani, K. A.; Rebak, R. B.
Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. ed. / Michael Wright; Denise Paraventi; John H. Jackson. Springer International Publishing, 2018. p. 235-244 (Minerals, Metals and Materials Series; Vol. Part F11).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

TY - GEN

T1 - Steam oxidation behavior of FeCrAl cladding

AU - Pint, B. A.

AU - Terrani, K. A.

AU - Rebak, R. B.

N1 - Publisher Copyright: © The Minerals, Metals & Materials Society 2018.

PY - 2018

Y1 - 2018

N2 - In order to better understand the high temperature steam oxidation behavior of FeCrAl alloys, this study addressed two topics. The first is continuing to evaluate the effect of alloy composition on performance of commercial and laboratory-made candidate FeCrAl alloys. For a few optimized compositions, this includes the performance of commercially-made tubing where it is clear that dropping the Cr content from 20% to 10–13% reduces the maximum operating temperature in steam by ~50 °C. The second addresses more realistic accident conditions. Model FeCrAl compositions that were exposed in ~300 °C water for 1 year were subsequently “ramp” tested in steam at 5 °C/min to 1500 °C to assess the effect of the Fe-rich oxide formed in water on the subsequent steam oxidation resistance. For Fe-18Cr-3Al+Y, the 1 year exposures in three different LWR water chemistries did not affect the ability to form alumina to 1500 °C. However, for marginal alloys Fe-13Cr-4Al and Fe-10Cr-5Al, some specimens began forming voluminous Fe-rich oxide at lower temperatures.

AB - In order to better understand the high temperature steam oxidation behavior of FeCrAl alloys, this study addressed two topics. The first is continuing to evaluate the effect of alloy composition on performance of commercial and laboratory-made candidate FeCrAl alloys. For a few optimized compositions, this includes the performance of commercially-made tubing where it is clear that dropping the Cr content from 20% to 10–13% reduces the maximum operating temperature in steam by ~50 °C. The second addresses more realistic accident conditions. Model FeCrAl compositions that were exposed in ~300 °C water for 1 year were subsequently “ramp” tested in steam at 5 °C/min to 1500 °C to assess the effect of the Fe-rich oxide formed in water on the subsequent steam oxidation resistance. For Fe-18Cr-3Al+Y, the 1 year exposures in three different LWR water chemistries did not affect the ability to form alumina to 1500 °C. However, for marginal alloys Fe-13Cr-4Al and Fe-10Cr-5Al, some specimens began forming voluminous Fe-rich oxide at lower temperatures.

KW - AlO

KW - FeCrAl

KW - Fuel cladding

KW - High temperature oxidation

KW - Steam

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M3 - Conference contribution

AN - SCOPUS:85042461284

SN - 9783319684536

T3 - Minerals, Metals and Materials Series

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EP - 244

BT - Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors

A2 - Wright, Michael

A2 - Paraventi, Denise

A2 - Jackson, John H.

PB - Springer International Publishing

T2 - 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2017

Y2 - 13 August 2017 through 17 August 2017

ER -

Pint BA, Terrani KA, Rebak RB. Steam oxidation behavior of FeCrAl cladding. In Wright M, Paraventi D, Jackson JH, editors, Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. Springer International Publishing. 2018. p. 235-244. (Minerals, Metals and Materials Series). doi: 10.1007/978-3-319-68454-3_20

Steam oxidation behavior of FeCrAl cladding

Abstract

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Keywords

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