Features of fracture faces in synroc C

S. Myhra , H.E. Bishop, J.C. Rivière
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引用次数: 2

Abstract

Fracture faces and polished surfaces of Synroc C specimens with 10% and 20% simulated high-level nuclear waste (HLW) have been studied with X-ray photoelectron spectroscopy. Elemental abundances and chemical environments for all matrix and most HLW atomic species have been investigated in the surface and near-surface layers before and after chemical attack. These observations suggest that the fracture mechanism is mainly intergranular, that particular phases are not preferentially exposed in the fracture faces, that some HLW species (caesium and molybdenum) are found in the grain boundaries, that intergranular regions are thin amorphous films or larger “glassy” triple points and that the intergranular films exhibit low chemical durability in an aqueous environment. These effects are independent of waste loading up to 20% and are consistent with the very good chemical durability reported for large monoliths.

同步型C型骨折面特征
用x射线光电子能谱对含10%和20%模拟高放核废料(HLW)的Synroc C试样的断口表面和抛光表面进行了研究。研究了化学腐蚀前后所有基体和大多数高分子量原子种类的表面和近表层元素丰度和化学环境。这些观察结果表明,断裂机制主要是在晶间断裂,特定相在断裂面不优先暴露,一些高放射性物质(铯和钼)存在于晶界中,晶间区域是薄的非晶膜或更大的“玻璃”三重点,晶间膜在水环境中表现出较低的化学耐久性。这些效果与高达20%的废物负荷无关,并且与报道的大型巨石非常好的化学耐久性相一致。
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