Interaction of beryllium with 316H stainless steel in molten Li2BeF4 (FLiBe)

Keiser, Jim R.; Singh, Preet Mohinder; Lance, Michael J.; Meyer III, Harry M.; Myhre, Kristian G.; Lowe, Tracie M.; Sulejmanovic, Dino; Cakmak, Ercan; Cox, Victoria A.; Hawkins, Charles Shane; Willoughby, Adam W.

doi:10.1016/j.jnucmat.2022.153698

Title: Interaction of beryllium with 316H stainless steel in molten Li₂BeF₄(FLiBe)

Abstract

The increased demand in renewable energy resources has led to a renewed interest in nuclear reactors including a new generation of molten salt reactors. One of the issues encountered in handling of molten chloride or fluoride salts is the inability of metals to form and retain a protective oxide surface layer, generally chromium oxide. The low chromium content, nickel-based alloy INOR-8, later marketed as Hastelloy N, was specifically developed to contain molten fluorides. This alloy had some deficiencies, but its composition resulted in it incurring far less chromium depletion by the molten fluoride salts than alloys like 316 stainless steel. For the next generation of molten salt reactors, an alloy with pressure vessel code approval and higher temperature capability than Hastelloy N is required. Consequently, several reactor designers have reportedly chosen to build the reactor containment vessel from 316H stainless steel. In order to minimize corrosion of the stainless steel by the molten fluoride salt (2LiF-BeF₂), it is proposed to add beryllium metal to the salt to react with impurities and provide a means to lower the oxidation potential thus making the salt less corrosive. Even so, there is a concern whether the beryllium would react with components of themore »« less

Authors:

^[1];

^[2];

^[1];

^[1]; Lowe, Tracie M. ^[1];

^[1];

^[1]; Hawkins, Charles Shane ^[1]; Willoughby, Adam W. ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Georgia Institute of Technology, Atlanta, GA (United States)

Publication Date:: Mon Apr 04 00:00:00 EDT 2022

Research Org.:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE)

OSTI Identifier:: 1866708

Alternate Identifier(s):: OSTI ID: 1961034

Grant/Contract Number:: AC05-00OR22725; NE0008749

Resource Type:: Accepted Manuscript

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Volume: 565; Journal Issue: July; Journal ID: ISSN 0022-3115

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 36 MATERIALS SCIENCE

Citation Formats


                    Keiser, Jim R., Singh, Preet Mohinder, Lance, Michael J., Meyer III, Harry M., Myhre, Kristian G., Lowe, Tracie M., Sulejmanovic, Dino, Cakmak, Ercan, Cox, Victoria A., Hawkins, Charles Shane, and Willoughby, Adam W. Interaction of beryllium with 316H stainless steel in molten Li2BeF4 (FLiBe).  United States: N. p., 2022. 
Web.  doi:10.1016/j.jnucmat.2022.153698.

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                    Keiser, Jim R., Singh, Preet Mohinder, Lance, Michael J., Meyer III, Harry M., Myhre, Kristian G., Lowe, Tracie M., Sulejmanovic, Dino, Cakmak, Ercan, Cox, Victoria A., Hawkins, Charles Shane, & Willoughby, Adam W. Interaction of beryllium with 316H stainless steel in molten Li2BeF4 (FLiBe).  United States.  https://doi.org/10.1016/j.jnucmat.2022.153698

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                    Keiser, Jim R., Singh, Preet Mohinder, Lance, Michael J., Meyer III, Harry M., Myhre, Kristian G., Lowe, Tracie M., Sulejmanovic, Dino, Cakmak, Ercan, Cox, Victoria A., Hawkins, Charles Shane, and Willoughby, Adam W. Mon .  
"Interaction of beryllium with 316H stainless steel in molten Li2BeF4 (FLiBe)".  United States.  https://doi.org/10.1016/j.jnucmat.2022.153698.  https://www.osti.gov/servlets/purl/1866708.

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@article{osti_1866708,

  title        = {Interaction of beryllium with 316H stainless steel in molten Li2BeF4 (FLiBe)},

  author       = {Keiser, Jim R. and Singh, Preet Mohinder and Lance, Michael J. and Meyer III, Harry M. and Myhre, Kristian G. and Lowe, Tracie M. and Sulejmanovic, Dino and Cakmak, Ercan and Cox, Victoria A. and Hawkins, Charles Shane and Willoughby, Adam W.},

  abstractNote = {The increased demand in renewable energy resources has led to a renewed interest in nuclear reactors including a new generation of molten salt reactors. One of the issues encountered in handling of molten chloride or fluoride salts is the inability of metals to form and retain a protective oxide surface layer, generally chromium oxide. The low chromium content, nickel-based alloy INOR-8, later marketed as Hastelloy N, was specifically developed to contain molten fluorides. This alloy had some deficiencies, but its composition resulted in it incurring far less chromium depletion by the molten fluoride salts than alloys like 316 stainless steel. For the next generation of molten salt reactors, an alloy with pressure vessel code approval and higher temperature capability than Hastelloy N is required. Consequently, several reactor designers have reportedly chosen to build the reactor containment vessel from 316H stainless steel. In order to minimize corrosion of the stainless steel by the molten fluoride salt (2LiF-BeF2), it is proposed to add beryllium metal to the salt to react with impurities and provide a means to lower the oxidation potential thus making the salt less corrosive. Even so, there is a concern whether the beryllium would react with components of the stainless steel. To address this concern, static capsule tests were conducted in which selected amounts of beryllium were added to capsules containing 2LiF-BeF2 (FLiBe) salt and 316H stainless steel and Hastelloy N samples. Following exposure, the samples were cleaned and examined using a variety of analysis techniques including, optical microscopy, SEM-EDS, XPS, LIBS, XRD and EPMA. Tensile samples were also exposed in capsules, and those were subjected to tensile testing. Notably, It was found that for the level of beryllium additions used in this study, intermetallic compounds were formed which could be detrimental to the long-term performance of the 316H stainless steel.},

  doi          = {10.1016/j.jnucmat.2022.153698},

  journal      = {Journal of Nuclear Materials},

  number       = July,

  volume       = 565,

  place        = {United States},

  year         = {Mon Apr 04 00:00:00 EDT 2022},

  month        = {Mon Apr 04 00:00:00 EDT 2022}

}

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Similar Records

Title: Interaction of beryllium with 316H stainless steel in molten Li2BeF4 (FLiBe)

Abstract

Citation Formats

Alloy compatibility with LiF--BeF₂ salts containing ThF₄ and UF₄ report, December 1972

Corrosion behaviour of stainless steels and a single crystal superalloy in a ternary LiCl–KCl–CsCl molten salt journal, January 2015

Compatibility of molten salts with type 316 stainless steel and lithium journal, December 1979

Corrosion of 316 stainless steel in high temperature molten Li2BeF4 (FLiBe) salt journal, June 2015

Batch-Scale Hydrofluorination of Li27BeF4 to Support Molten Salt Reactor Development journal, September 2015

Control of molten salt corrosion of fusion structural materials by metallic beryllium journal, April 2009

Effects of exposing duration on corrosion performance in weld joint of Ni-Mo-Cr alloy in FLiNaK molten salt journal, November 2016

The Be−Cr (Beryllium-Chromium) system journal, February 1986

The molten salt reactor (MSR) in generation IV: Overview and perspectives journal, November 2014

Molten-Salt Reactors—History, Status, and Potential journal, February 1970

The Be−Ni (Beryllium-Nickel) system journal, October 1988

Materials corrosion in molten LiF–NaF–KF salt journal, January 2009

Reaction rate of beryllium with fluorine ion for Flibe redox control journal, August 2007

Alloys compatibility in molten salt fluorides Kurchatov Institute related experience journal, October 2013

High Performance Corrosion Resistance of Nickel-Based Alloys in Molten Salt Flibe journal, July 2009

Preparation and Handling of Salt Mixtures for the Molten Salt Reactor Experiment report, January 1971

Corrosion-induced microstructural developments in 316 stainless steel during exposure to molten Li2BeF4(FLiBe) salt journal, December 2016

Effect of moisture on corrosion of Ni-based alloys in molten alkali fluoride FLiNaK salt environments journal, June 2013

Redox potential control in molten salt systems for corrosion mitigation journal, November 2018

Long-term corrosion behaviors of Hastelloy-N and Hastelloy-B3 in moisture-containing molten FLiNaK salt environments journal, March 2014

Corrosion of Incoloy 800H alloys with nickel cladding in FLiNaK salts at 850 °C journal, April 2018

Effect of Li metal addition on corrosion control of Hastelloy N and stainless steel 316H in molten LiF-NaF-KF journal, November 2021

Compatibility studies of potential molten-salt breeder reactor materials in molten fluoride salts. [Inconel 601, Cr and Nb modifications of Hastelloy N] report, May 1977

Title: Interaction of beryllium with 316H stainless steel in molten Li₂BeF₄(FLiBe)

Alloy compatibility with LiF--BeF₂ salts containing ThF₄ and UF₄
report, December 1972

Corrosion behaviour of stainless steels and a single crystal superalloy in a ternary LiCl–KCl–CsCl molten salt
journal, January 2015

Compatibility of molten salts with type 316 stainless steel and lithium
journal, December 1979

Corrosion of 316 stainless steel in high temperature molten Li₂BeF₄ (FLiBe) salt
journal, June 2015

Batch-Scale Hydrofluorination of Li27BeF4 to Support Molten Salt Reactor Development
journal, September 2015

Control of molten salt corrosion of fusion structural materials by metallic beryllium
journal, April 2009

Effects of exposing duration on corrosion performance in weld joint of Ni-Mo-Cr alloy in FLiNaK molten salt
journal, November 2016

The Be−Cr (Beryllium-Chromium) system
journal, February 1986

The molten salt reactor (MSR) in generation IV: Overview and perspectives
journal, November 2014

Molten-Salt Reactors—History, Status, and Potential
journal, February 1970

The Be−Ni (Beryllium-Nickel) system
journal, October 1988

Materials corrosion in molten LiF–NaF–KF salt
journal, January 2009

Reaction rate of beryllium with fluorine ion for Flibe redox control
journal, August 2007

Alloys compatibility in molten salt fluorides Kurchatov Institute related experience
journal, October 2013

High Performance Corrosion Resistance of Nickel-Based Alloys in Molten Salt Flibe
journal, July 2009

Preparation and Handling of Salt Mixtures for the Molten Salt Reactor Experiment
report, January 1971

Corrosion-induced microstructural developments in 316 stainless steel during exposure to molten Li2BeF4(FLiBe) salt
journal, December 2016

Effect of moisture on corrosion of Ni-based alloys in molten alkali fluoride FLiNaK salt environments
journal, June 2013

Redox potential control in molten salt systems for corrosion mitigation
journal, November 2018

Long-term corrosion behaviors of Hastelloy-N and Hastelloy-B3 in moisture-containing molten FLiNaK salt environments
journal, March 2014

Corrosion of Incoloy 800H alloys with nickel cladding in FLiNaK salts at 850 °C
journal, April 2018

Effect of Li metal addition on corrosion control of Hastelloy N and stainless steel 316H in molten LiF-NaF-KF
journal, November 2021

Compatibility studies of potential molten-salt breeder reactor materials in molten fluoride salts. [Inconel 601, Cr and Nb modifications of Hastelloy N]
report, May 1977