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51317--9497-Corrosion Evaluation of Alloys For High Temperature Service in Molten Fluoride Salt Cooled Reactors

Picture for Corrosion Evaluation of Alloys For High Temperature Service in Molten Fluoride Salt Cooled Reactors
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Nickel based alloys are candidate materials for high temperature structural applications in Fluoride Salt Cooled High Temperature Reactors. This study presents preliminary data on the corrosion behavior of selected experimental Nickel alloys in 46.5 LiF-11.5 NaF-42.0 KF (FLiNaK).

Product Number: 51317--9497-SG
ISBN: 9497 2017 CP
Author: Govindarajan Muralidharan
Publication Date: 2017
Industry: Energy Generation
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Fluoride-salt cooled reactors are a class of reactors that have attractive performance and safety attributes. The defining features ofthese flouride salt cooled high temperature reactors(FHR's) are high-temperature heat production and the use of low-pressure fluoride salt cooling.Although fluoride salts have attractive heat-transfer characteristics materials in contact with these salts are subject to corrosive attack. Oxide scales that are traditionally used for high temperature protection are removed when the material is in contact with fluoride salts and hence the composition of the alloy has a significant effect on the corrosion behavior in molten salts.This paper will present the techniques used for the laboratory-scale corrosion evaluation of alloys for service at high temperatures in molten fluoride salt environments.A brief overview of the effect of alloying elements on the fluoride salt corrosion will be provided. Behavior of existing alloys such as Alloy N in liquid FLiNaK will be compared to that of new developmental alloys.This work was funded by theLDRD Program Oak Ridge National Laboratory. Oak Ridge National Laboratory is managed by UT-Battelle LLC under Contract No. DE-AC05-00OR22725 with the United States Department of Energy

Key words: Fluoride salt cooled reactors, FLiNaK, Ni-based alloys

Fluoride-salt cooled reactors are a class of reactors that have attractive performance and safety attributes. The defining features ofthese flouride salt cooled high temperature reactors(FHR's) are high-temperature heat production and the use of low-pressure fluoride salt cooling.Although fluoride salts have attractive heat-transfer characteristics materials in contact with these salts are subject to corrosive attack. Oxide scales that are traditionally used for high temperature protection are removed when the material is in contact with fluoride salts and hence the composition of the alloy has a significant effect on the corrosion behavior in molten salts.This paper will present the techniques used for the laboratory-scale corrosion evaluation of alloys for service at high temperatures in molten fluoride salt environments.A brief overview of the effect of alloying elements on the fluoride salt corrosion will be provided. Behavior of existing alloys such as Alloy N in liquid FLiNaK will be compared to that of new developmental alloys.This work was funded by theLDRD Program Oak Ridge National Laboratory. Oak Ridge National Laboratory is managed by UT-Battelle LLC under Contract No. DE-AC05-00OR22725 with the United States Department of Energy

Key words: Fluoride salt cooled reactors, FLiNaK, Ni-based alloys

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Corrosion of Ni-Based Alloys and Stainless Steels in Molten Fluoride Salts for Gen IV Reactors

Product Number: 51317--9132-SG
ISBN: 9132 2017 CP
Author: Kevin Chan
Publication Date: 2017
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Several Generation IV nuclear reactor concepts feature molten fluoride salt coolants. Corrosion of alloys in molten fluorides remains a challenge.  Static exposure tests of nickel-based alloys and austenitic stainless steels were conducted in the molten fluoride salt known as FLiNaK.
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51318-11182-Effects of Pre-Oxidiation and Carburization on Corrosion in Molten Fluoride Salts

Product Number: 51318-11182-SG
Author: Kevin J. Chan / Rebecca Ambrecht / Won Tae Choi / Preet M. Singh
Publication Date: 2018
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Static exposure tests of pre-oxidized stainless steel and carburized chromium were conducted in the molten fluoride salt, LiF-NaF-KF (46.5-11.5-42 mol %), FLiNaK to simulate the corrosion environment typical of some advanced nuclear reaction concepts.
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51317--9513-Monitoring Pitting Corrosion Growth in Steel Rebar Using Optical Fiber

Product Number: 51317--9513-SG
ISBN: 9513 2017 CP
Author: Fujian Tang
Publication Date: 2017
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An optical fiber corrosion sensor is developed to monitor the penetration of corrosion pits in steel bars. Simply made by encasing one end of an optical fiber into a steel straw. As corrosion penetrates the steel straw wall, the solution and corrosion products fill inside and contaminate the fiber end surface, resulting in a change in the reflectivity.
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