Corrosion evaluation of alloys for high temperature service in molten fluoride salt cooled reactors

G. Muralidharan; D. F. Wilson; J. R. Keiser

Corrosion evaluation of alloys for high temperature service in molten fluoride salt cooled reactors

G. Muralidharan, D. F. Wilson, J. R. Keiser

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

Abstract

Fluoride Salt Cooled High Temperature Reactors (FHRs) are important to the world as a potential future primary electricity source, with a very high potential that the present fleet of aging Light Water Reactors (LWRs) could be replaced by FHRs. As both the fuel and coolants for FHRs are suitable for very high temperature use (well in excess of 1000 °C), the limiting factor in achieving the highest possible FHR core outlet temperatures and thus thermal efficiency is the availability of compatible structural alloys. Nickel based alloys are candidate materials for high temperature structural applications where they excel in retaining strength, creep and oxidation resistance at high homologous temperatures. There is an extensive body of information on the corrosion of materials in molten fluoride salts as a result of the work performed at the Oak Ridge National Laboratory (ORNL) on fluoride cooled reactors in the 1950s and 1960s. However, very little data is available on alloys for performance in molten fluoride environments at temperatures greater than 750 °C. Furthermore, the effect of alloying elements on the resistance to molten fluoride environments is not known. This study presents preliminary data on the corrosion behavior of selected experimental alloys in 46.5 LiF-11.5 NaF-42.0 KF (FLiNaK).

Original language	English
Title of host publication	Corrosion Conference and Expo 2017
Publisher	National Assoc. of Corrosion Engineers International
Pages	4685-4691
Number of pages	7
ISBN (Electronic)	9781510840348
State	Published - 2017
Event	Corrosion Conference and Expo 2017 - New Orleans, United States Duration: Mar 26 2017 → Mar 30 2017

Publication series

Name	NACE - International Corrosion Conference Series
Volume	7
ISSN (Print)	0361-4409

Conference

Conference	Corrosion Conference and Expo 2017
Country/Territory	United States
City	New Orleans
Period	03/26/17 → 03/30/17

Funding

Research sponsored by the Laboratory Directed Research and Development Program of Oak Ridge National Laboratory, managed by UT-Battelle, LLC, for the U. S. Department of Energy. The authors would like to acknowledge the assistance of Cecil Carmichael, Dave Harper, Greg Cox, and Kevin Harper in casting, rolling, and heat-treatment of the alloys A and B. The assistance of Adam Willoughby in preparation of the corrosion test articles and conducting the corrosion tests, and Jordon Tyson in preparation and imaging of the cross-sections of the specimens is gratefully acknowledged.

Funders	Funder number
UT-Battelle
U.S. Department of Energy
Oak Ridge National Laboratory
Laboratory Directed Research and Development

Keywords

FLiNaK
Fluoride salt cooled reactors
Ni-based alloys

Cite this

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title = "Corrosion evaluation of alloys for high temperature service in molten fluoride salt cooled reactors",

abstract = "Fluoride Salt Cooled High Temperature Reactors (FHRs) are important to the world as a potential future primary electricity source, with a very high potential that the present fleet of aging Light Water Reactors (LWRs) could be replaced by FHRs. As both the fuel and coolants for FHRs are suitable for very high temperature use (well in excess of 1000 °C), the limiting factor in achieving the highest possible FHR core outlet temperatures and thus thermal efficiency is the availability of compatible structural alloys. Nickel based alloys are candidate materials for high temperature structural applications where they excel in retaining strength, creep and oxidation resistance at high homologous temperatures. There is an extensive body of information on the corrosion of materials in molten fluoride salts as a result of the work performed at the Oak Ridge National Laboratory (ORNL) on fluoride cooled reactors in the 1950s and 1960s. However, very little data is available on alloys for performance in molten fluoride environments at temperatures greater than 750 °C. Furthermore, the effect of alloying elements on the resistance to molten fluoride environments is not known. This study presents preliminary data on the corrosion behavior of selected experimental alloys in 46.5 LiF-11.5 NaF-42.0 KF (FLiNaK).",

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year = "2017",

language = "English",

series = "NACE - International Corrosion Conference Series",

publisher = "National Assoc. of Corrosion Engineers International",

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Muralidharan, G, Wilson, DF & Keiser, JR 2017, Corrosion evaluation of alloys for high temperature service in molten fluoride salt cooled reactors. in Corrosion Conference and Expo 2017. NACE - International Corrosion Conference Series, vol. 7, National Assoc. of Corrosion Engineers International, pp. 4685-4691, Corrosion Conference and Expo 2017, New Orleans, United States, 03/26/17.

Corrosion evaluation of alloys for high temperature service in molten fluoride salt cooled reactors. / Muralidharan, G.; Wilson, D. F.; Keiser, J. R.
Corrosion Conference and Expo 2017. National Assoc. of Corrosion Engineers International, 2017. p. 4685-4691 (NACE - International Corrosion Conference Series; Vol. 7).

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

TY - GEN

T1 - Corrosion evaluation of alloys for high temperature service in molten fluoride salt cooled reactors

AU - Muralidharan, G.

AU - Wilson, D. F.

AU - Keiser, J. R.

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N2 - Fluoride Salt Cooled High Temperature Reactors (FHRs) are important to the world as a potential future primary electricity source, with a very high potential that the present fleet of aging Light Water Reactors (LWRs) could be replaced by FHRs. As both the fuel and coolants for FHRs are suitable for very high temperature use (well in excess of 1000 °C), the limiting factor in achieving the highest possible FHR core outlet temperatures and thus thermal efficiency is the availability of compatible structural alloys. Nickel based alloys are candidate materials for high temperature structural applications where they excel in retaining strength, creep and oxidation resistance at high homologous temperatures. There is an extensive body of information on the corrosion of materials in molten fluoride salts as a result of the work performed at the Oak Ridge National Laboratory (ORNL) on fluoride cooled reactors in the 1950s and 1960s. However, very little data is available on alloys for performance in molten fluoride environments at temperatures greater than 750 °C. Furthermore, the effect of alloying elements on the resistance to molten fluoride environments is not known. This study presents preliminary data on the corrosion behavior of selected experimental alloys in 46.5 LiF-11.5 NaF-42.0 KF (FLiNaK).

AB - Fluoride Salt Cooled High Temperature Reactors (FHRs) are important to the world as a potential future primary electricity source, with a very high potential that the present fleet of aging Light Water Reactors (LWRs) could be replaced by FHRs. As both the fuel and coolants for FHRs are suitable for very high temperature use (well in excess of 1000 °C), the limiting factor in achieving the highest possible FHR core outlet temperatures and thus thermal efficiency is the availability of compatible structural alloys. Nickel based alloys are candidate materials for high temperature structural applications where they excel in retaining strength, creep and oxidation resistance at high homologous temperatures. There is an extensive body of information on the corrosion of materials in molten fluoride salts as a result of the work performed at the Oak Ridge National Laboratory (ORNL) on fluoride cooled reactors in the 1950s and 1960s. However, very little data is available on alloys for performance in molten fluoride environments at temperatures greater than 750 °C. Furthermore, the effect of alloying elements on the resistance to molten fluoride environments is not known. This study presents preliminary data on the corrosion behavior of selected experimental alloys in 46.5 LiF-11.5 NaF-42.0 KF (FLiNaK).

KW - FLiNaK

KW - Fluoride salt cooled reactors

KW - Ni-based alloys

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T3 - NACE - International Corrosion Conference Series

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BT - Corrosion Conference and Expo 2017

PB - National Assoc. of Corrosion Engineers International

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ER -

Corrosion evaluation of alloys for high temperature service in molten fluoride salt cooled reactors

Abstract

Publication series

Conference

Funding

Keywords

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