Thermal Analysis and Immobilisation of Spent Ion Exchange Resin in Borosilicate Glass
Thermal Analysis and Immobilisation of Spent Ion Exchange Resin in Borosilicate Glass
复制标题
废离子交换树脂在硼硅酸盐玻璃中的热分析和固定化
DOI：
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发表时间：
2012
期刊：
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通讯作者：
T. Abram
中科院分区：
文献类型：
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作者：
Nasir H. Hamodi;K. Papadopoulou;T. Lowe;T. Abram
核工业产生的废物的地下处置需要不断的评估，以便在不损害放射性废物形式的任何泄漏的安全的情况下，通过减少玻璃的使用量来最大限度地减少体积和成本来改进它。研究了废树脂（NRW-40）在硼硅酸盐玻璃中的固定化性能，以达到核废料处理的验收标准。以颗粒状有机混床树脂为废靶材料。对放射性和非放射性铯（Cs）和钴（Co）掺杂的替代树脂进行了分析，研究了它们的热学和化学性能以及与碱性硼硅酸盐玻璃的相容性。热分析表明，1 mSv伽马射线对放射性树脂造成的结构损伤与非放射性树脂相比，其性能发生了变化，两种树脂中使用了相同量的铯（8.88 wt%）和钴（1.88 wt%）。残渣的固定化表明，残渣中过量的硫在最终的玻璃基体中引起相结晶。结果表明，放射性树脂-玻璃基体（HG-3-IER-500）中Cs-137和Co-60的挥发量大于非放射性树脂-玻璃基体（HG-3-IEX-500）。该研究展示了全面的实验和分析工作，并表明在保持所需的安全水平的同时尽量减少废物量是可能的，但需要在这方面进行进一步的研究。
The underground disposal of waste arising from the nuclear industry needs constant evaluation in order to improve upon it through minimizing the volume and cost by reducing the amount of glass used without compromising the safety of any leakage from the radioactive waste form. The immobilization of the spent resin (NRW-40) in borosilicate glass was investigated to meet the acceptance criteria for disposal of nuclear waste. The organic mixed bed resin in granular form was used as a waste target. The analysis of surrogate resin doped with radioactive and non-radioactive cesium (Cs) and cobalt (Co) was carried out to investigate their thermal and chemical properties and their compatibility with an alkaline borosilicate glass. The thermal analysis indicates that the structural damage caused by 1 mSv gamma radiation to the radioactive resin has altered its properties in comparison with the non-radioactive resin, same amount of cesium (8.88 wt%) and cobalt (1.88 wt%) were used in both resins. The immobilization of residue shows that the excess sulfur in the residue caused phase crystallization in the final glass matrix. It was found that the volatilization of Cs-137 and Co-60 from the successful radioactive resin-glass matrix (HG-3-IER-500) were more than that in the non-radioactive resin-glass matrix (HG-3-IEX-500). The study demonstrates comprehensive experimental and analytical works and shows that it is possible to minimise the volume of the waste while keeping the required safety levels, however further research needs to be carried out in this area.