首页> 外文会议>American Nuclear Society;International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors >CHARACTERIZATION OF MICROSTRUCTURE OF ALLOY 52M WELD METAL NEAR THE FUSION BOUNDARY AND OXIDE FILMS FORMED IN SIMULATED PWR PRIMARY WATER
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CHARACTERIZATION OF MICROSTRUCTURE OF ALLOY 52M WELD METAL NEAR THE FUSION BOUNDARY AND OXIDE FILMS FORMED IN SIMULATED PWR PRIMARY WATER

机译:模拟压水堆原水中熔合边界和氧化物膜附近的52M合金焊接金属的微观组织特征

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Alloy 52M weld metal samples are taken fromlocations at distances of 1.1 mm, 2.3 mm, 10 mm awayfrom the fusion boundary (FB) to low alloy steel,representing the first dilution zone, the second dilutionzone and the undiluted zone of Alloy 52M butteringlayer. Cr and Ni contents in the second dilution zone arelower than that in the first dilution zone, which arehigher than that in the undiluted zone. Oxide filmsformed on these Alloy 52M samples in simulatedpressurized water reactor (PWR) primary water at 325°C are duplex-layered with the Fe-rich outer oxide layerof large and scattered particles, and the Cr-rich innerlayer of small and dense particles. With increasing thedistance from the fusion boundary, the thickness of theinner oxide layer decreases. Cr oxide along the grainboundary is observed. The change of main alloyelements and the resultant change of oxidation behaviorin PWR primary water are consistent with the observedSCC behavior.
机译:合金52M焊接金属样本取自 距离1.1 mm,2.3 mm,10 mm的位置 从熔合边界(FB)到低合金钢, 代表第一个稀释区,第二个稀释区 52M黄油涂脂区和未稀释区 层。第二稀释区中的Cr和Ni含量为 低于第一稀释区的 高于未稀释区。氧化膜 在模拟中在这些52M合金样品上形成 压水堆(PWR)初级水温325 °C与富铁外部氧化物层成双层 大而分散的颗粒,以及富含Cr的内部 小而密的颗粒层。随着增加 距融合边界的距离, 内氧化物层减少。沿晶粒的氧化铬 边界被观察到。主要合金的变化 元素及其氧化行为的变化 在压水堆的原水中与观察到的一致 SCC行为。

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