A new approach to the immobilisation of technetium and transuranics: Co-disposal in a zirconolite ceramic matrix

A new approach to the immobilisation of technetium and transuranics: Co-disposal in a zirconolite ceramic matrix
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固定锝和超铀的新方法:在锆英石陶瓷基质中的共同处置

DOI:
10.1016/j.jnucmat.2019.151885
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发表时间:
2020
影响因子:
3.1
通讯作者:
Bailey D
Bailey D
中科院分区:
工程技术2区
文献类型:
--
作者:
Bailey D

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锝和超铀元素(TRUs)是长寿命的放射性核素,由核能发电产生。这些放射性核素在陶瓷废物中的共固定是有吸引力的,因为它们对于玻璃化是有问题的,并且将减少对未来地质处置设施的需求。以钼和铈为替代物,通过氧化物路线制备了一系列锆英石陶瓷,以期实现Tc和TRUs的共固定。采用XRD、SEM-EDX、TEM和XAS等手段对材料进行了表征。最终相组合被发现是由目标化学计量,所使用的Ca前体,加工温度和加工气氛的影响。通过适当的优化处理条件和目标化学计量,本研究的结果表明,共固定的Tc和TRUs是一种很有前途的方法。
Technetium and transuranic elements (TRUs) are long-lived radionuclides, produced as a result of nuclear power generation. Co-immobilisation of these radionuclides in a ceramic wasteform is attractive as they are problematic for vitrification and would reduce the demand on a future geological disposal facility. A range of zirconolite ceramics have been producedviaan oxide route using the surrogates Mo and Ce with a view to the co-immobilisation of Tc and TRUs. The resultant materials were characterised by XRD, SEM-EDX, TEM and XAS. Final phase assemblage was found to be affected by target stoichiometry, the Ca precursor used, processing temperature and processing atmosphere. Through appropriate optimisation of processing conditions and target stoichiometry, the results of this study show co-immobilisation of Tc and TRUs is a promising approach.
作为潜在废物形式的含锝烧绿石和钙钛矿的制备和性能
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