Thermal treatment of nuclear fuel-containing Magnox sludge radioactive waste

Thermal treatment of nuclear fuel-containing Magnox sludge radioactive waste
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含核燃料 Magnox 污泥放射性废物的热处理

DOI:
10.1016/j.jnucmat.2021.152965
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发表时间:
2021
影响因子:
3.1
通讯作者:
Barlow S
Barlow S
中科院分区:
工程技术2区
文献类型:
--
作者:
Barlow S

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镁铝硅酸盐和镁硼硅酸盐玻璃配方的开发和评价的放射性废物称为镁诺克斯污泥的固定。使用两种简化的结合废物模拟物合成玻璃组合物,所述模拟物包括在高达50重量%的废物负荷下的腐蚀的和金属的铀和镁。玻璃固定腐蚀的模拟废物形成一般均匀和完全无定形的玻璃,而那些固定金属废物含有UO 2和U3 O 8的微晶。玻璃内的铀形态进行了研究,通过微焦点X-射线吸收近边光谱,结果表明,硼硅酸盐玻璃组合物的特征在于由一个略低的平均铀氧化态比铝硅酸盐对应物。这对耐久性产生了影响,平均氧化态较高的玻璃中的铀更容易溶解。所有材料显示出与模拟高水平放射性废物玻璃相当的溶解速率,而硼硅酸盐基制剂在适合于放射性废物应用中使用的现代玻璃化技术的温度下熔化。这些数据突出了硼硅酸盐或铝硅酸盐玻璃配方中危险放射性镁诺克斯污泥废物的玻璃化潜力,有可能实现比当前基线计划减少> 95%的调节废物体积。
Magnesium aluminosilicate and magnesium borosilicate glass formulations were developed and evaluated for the immobilisation of the radioactive waste known as Magnox sludge. Glass compositions were synthesised using two simplified bounding waste simulants, including corroded and metallic uranium and magnesium at waste loadings of up to 50 wt.%. The glasses immobilising corroded simulant waste formed generally homogenous and fully amorphous glasses, while those immobilising metallic wastes contained crystallites of UO2and U3O8. Uranium speciation within the glass was investigated by micro-focus X-ray absorption near edge spectroscopy and it was shown that the borosilicate glass compositions were characterised by a slightly lower mean uranium oxidation state than the aluminosilicate counterparts. This had an impact upon the durability, and uranium within glasses of higher mean oxidation states was dissolved more readily. All material showed dissolution rates that were comparable with simulant high level radioactive waste glasses, while the borosilicate-based formulations melted at a temperature suitable for modern vitrification technologies used in radioactive waste applications. These data highlight the potential for vitrification of hazardous radioactive Magnox sludge waste in borosilicate or aluminosilicate glass formulations, with the potential to achieve >95 % reduction in conditioned waste volume over the current baseline plan.
高活性放射性废物的容器内玻璃化产品的多废物流的表征和可处置性评估。
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