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作为用于铯和碘封存的潜在主体相的CsPbI的化学耐久性和降解机制。

Chemical durability and degradation mechanisms of CsPbI as a potential host phase for cesium and iodine sequestration.

作者信息

Bryce Keith, Yang Kun, Wang Yachun, Lian Jie

机构信息

Department of Mechanical, Aerospace and Nuclear Engineering, Rensselaer Polytechnic Institute NY 12180 USA

Department of Materials Science & Engineering, Rensselaer Polytechnic Institute NY 12180 USA.

出版信息

RSC Adv. 2022 Apr 22;12(20):12242-12252. doi: 10.1039/d2ra01259f.

Abstract

Effective nuclear waste management of radioactive cesium and off-gas iodine from complex waste streams of used fuels is essential for the sustainable development of advanced nuclear fuel cycles. Once cesium and iodine are separated from their respective waste streams, host phases are required to immobilize them into a durable waste form matrix for long-term disposition. The inorganic metal halide perovskite, CsPbI, has a unique crystal structure capable of incorporating both cesium and iodine simultaneously. Exposure to groundwater in geological repositories is a long-term concern for waste forms, as this may cause corrosion and decrease the waste form's ability to retain radionuclides. In this study, we explore the potential of CsPbI perovskite as a promising host phase to incorporate Cs and I, and investigate its chemical durability and degradation mechanisms in an aqueous environment. CsPbI was synthesized through a solution-based method and was consolidated into dense pellets by spark plasma sintering. The chemical durability of the CsPbI pellets was evaluated by static leaching tests in deionized water at different temperatures of 25, 58, and 90 °C. The elemental release mechanisms and surface alteration of the monolithic CsPbI pellets were investigated. Both I and Cs displayed a non-congruent leaching behavior and faster release rates as compared to Pb, particularly at longer leaching durations and higher temperatures. At the initial leaching stage, a PbI alteration layer formed on the surface of the pellet due to the rapid release of Cs and I, followed by the formation of a PbI(OH) alteration layer. The activation energies for both dissolution and diffusion controlled mechanisms were determined to be 44.90 kJ mol and 45.40 kJ mol for Pb, 27.10 kJ mol and 40.82 kJ mol for I and 24.27 kJ mol and 23.86 kJ mol for Cs, respectively. These results show a clear decrease in activation energies from Pb to I and Cs, suggesting a preferential release of I and Cs. The solution-based synthesis of CsPbI as a host phase for Cs and I and the fundamental understanding of the chemical durability and degradation behavior will be useful for further exploring its application for immobilizing iodine and cesium into final durable waste forms for long-term geological disposition.

摘要

对乏燃料复杂废物流中的放射性铯和废气碘进行有效的核废物管理,对于先进核燃料循环的可持续发展至关重要。一旦铯和碘从各自的废物流中分离出来,就需要主体相将它们固定在一种耐用的废物形式基质中,以便长期处置。无机金属卤化物钙钛矿CsPbI具有独特的晶体结构,能够同时容纳铯和碘。地质储存库中的地下水暴露是废物形式长期关注的问题,因为这可能导致腐蚀并降低废物形式保留放射性核素的能力。在本研究中,我们探索了CsPbI钙钛矿作为一种有前景的主体相来容纳铯和碘的潜力,并研究了其在水环境中的化学耐久性和降解机制。通过基于溶液的方法合成了CsPbI,并通过放电等离子烧结将其固结为致密的颗粒。通过在25、58和90°C的不同温度下在去离子水中进行静态浸出试验,评估了CsPbI颗粒的化学耐久性。研究了整体CsPbI颗粒的元素释放机制和表面变化。与铅相比,碘和铯均表现出非一致的浸出行为和更快的释放速率,特别是在更长的浸出时间和更高的温度下。在浸出初始阶段,由于铯和碘的快速释放,在颗粒表面形成了一层PbI蚀变层,随后形成了一层PbI(OH)蚀变层。确定溶解和扩散控制机制的活化能,铅分别为44.90 kJ mol和45.40 kJ mol,碘为27.10 kJ mol和40.82 kJ mol,铯为24.27 kJ mol和23.86 kJ mol。这些结果表明从铅到碘和铯活化能明显降低,表明碘和铯优先释放。基于溶液合成CsPbI作为铯和碘的主体相以及对化学耐久性和降解行为的基本理解,将有助于进一步探索其在将碘和铯固定到最终耐用废物形式中以进行长期地质处置方面的应用。

https://cdn.ncbi.nlm.nih.gov/pmc/blobs/2656/9026147/1d83055ab81d/d2ra01259f-f1.jpg

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