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Accession Number
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DE2012-1045757
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Title
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Report on Sodium Compatibility of Advanced Structured Materials.
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Publication Date
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Sep 2011
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Media Count
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38p
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Personal Author
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D. L. Rink J. T. Listwan K. Natesan M. Li W. K. Soppet Y. Momozaki
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Abstract
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This report provides an update on the evaluation of sodium compatibility of advanced structural materials. The report is a deliverable (level 3) in FY11 (M3A11AN04030403), under the Work Package A-11AN040304, 'Sodium Compatibility of Advanced Structural Materials' performed by Argonne National Laboratory (ANL), as part of Advanced Structural Materials Program for the Advanced Reactor Concepts. This work package supports the advanced structural materials development by providing corrosion and tensile data from the standpoint of sodium compatibility of advanced structural alloys. The scope of work involves exposure of advanced structural alloys such as G92, mod.9Cr-1Mo (G91) ferritic-martensitic steels and HT-UPS austenitic stainless steels to a flowing sodium environment with controlled impurity concentrations. The exposed specimens are analyzed for their corrosion performance, microstructural changes, and tensile behavior. Previous reports examined the thermodynamic and kinetic factors involved in the purity of liquid sodium coolant for sodium reactor applications as well as the design, fabrication, and construction of a forced convection sodium loop for sodium compatibility studies of advanced materials. This report presents the results on corrosion performance, microstructure, and tensile properties of advanced ferritic-martensitic and austenitic alloys exposed to liquid sodium at 550 C for up to 2700 h and at 650 C for up to 5064 h in the forced convection sodium loop. The oxygen content of sodium was controlled by the cold-trapping method to achieve (approx)1 wppm oxygen level.
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Keywords
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Alloys
Austentic steels
Building materials
Compatibility
Coolants
Corrosion
Elongation
Fabrication
Ferrite
Forced convection
Kinetics
Martensite
Nuclear reactors
Oxygen
Recrystallization
Sodium
Stainless steels
Strain gaging
Tensile properties
Thermodynamics
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Source Agency
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Technical Information Center Oak Ridge Tennessee
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NTIS Subject Category
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71 - Materials Sciences
77H - Reactor Engineering & Nuclear Power Plants
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Corporate Author
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Argonne National Lab., IL. Nuclear Engineering Div.
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Document Type
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Technical report
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Title Note
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N/A
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NTIS Issue Number
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1303
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Contract Number
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DE-AC02-06CH11357
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