Thermal Aging of Dissimilar-Metal Weld Joints for Reactor Pressurized Vessels at Elevated Temperature

Won Sik Kong; Chung Seok Kim

doi:10.4028/www.scientific.net/MSF.857.271

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HomeMaterials Science ForumMaterials Science Forum Vol. 857Thermal Aging of Dissimilar-Metal Weld Joints for...

Thermal Aging of Dissimilar-Metal Weld Joints for Reactor Pressurized Vessels at Elevated Temperature

Abstract:

The purpose of this study is to investigate the thermal aging of dissimilar metal welds for reactor pressurized vessels in the primary system of nuclear power plants. The influences of long-term aging of dissimilar-metal welds on microstructural and mechanical characteristics have been studied qualitatively and quantitatively. The dissimilar-metal welds composed of SA 508 Cl.3 low alloy steel and AISI 316L stainless steel are prepared after buttering alloy 82 on the SA 508 side by the gas tungsten arc welding process using Inconel 82 welding consumable. The test specimens are heat-treated at 600°C for 10000 hours at each predetermined aging time to simulate the degraded microstructure of dissimilar-metal welds subjected to high temperature and pressure. The long-term aging tests are interrupted at various stages to obtain the different level of degraded specimens. The microstructural changes in base metals and weld metal have been evaluated by the optical and electron microscope in relation with twins, grains, precipitates, and phase transformation. The residual stress and mechanical softening were also discussed in terms of microstructural changes during long-term aging.

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Materials Science Forum (Volume 857)

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271-275

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https://doi.org/10.4028/www.scientific.net/MSF.857.271

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Online since:

May 2016

Authors:

Won Sik Kong, Chung Seok Kim*

Keywords:

Aging, Dissimilar-Metal, Elevated Temperature, Vessels, Welds

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