Influence of Sodium on the Tensile Properties of Optimized Grade 92 Steel

Technical Report · Wed Jul 01 04:00:00 EDT 2015

DOI:https://doi.org/10.2172/1879650· OSTI ID:1879650

Natesan, K. ^[1]; Li, Meimei ^[1]; Chen, Wei-Ying ^[1]; Momozaki, Y. ^[1]; Rink, D. L. ^[1]

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1. Argonne National Lab. (ANL), Argonne, IL (United States)

This report provides an update on the evaluation of sodium compatibility of advanced alloy, optimized Grade 92, and the reference materials. The report is a deliverable (Level 3) in FY15 (M3AT-15AN1602072), under the Work Package AR-15AN160207, “Sodium Compatibility” performed by Argonne National Laboratory (ANL), as part of Advanced Reactor Technologies program. This work package supports the advanced structural materials development by providing corrosion, microstructure, and tensile property data from the standpoint of sodium compatibility of advanced structural alloys. During this fiscal year, sodium exposure experiments were performed at 600°C in forced convection sodium loops at Argonne National Laboratory. The oxygen content of sodium was controlled by the cold-trapping method to achieve ≈1 wppm oxygen level. Specimens were removed from the sodium loop after a pre-determined exposure time for post-sodium-exposure-examination, including weight and thickness measurements, cross-sectional examinations, microhardness measurements, microstructural characterization, and tensile tests at the sodium exposure temperature. Data of sodium-exposed specimens were compared with thermal aging data obtained at 650°C to separate the effects of sodium exposures and thermal aging. This report adds to the results on corrosion performance, microstructure and tensile properties of ferritic-martensitic exposed to sodium at 600°C. Specimens of G92-0, Opt. G92-4, Opt. G92-4T, and G91-H30176 for times up to 8,200 h, and Opt. G92-8T for 1,653 h were exposed to sodium at 600°C.

• Research Organization: Argonne National Laboratory (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC02-06CH11357
• OSTI ID: 1879650
• Report Number(s): ANL-ART-9; 122428
• Country of Publication: United States
• Language: English

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36 MATERIALS SCIENCE