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Performance of cemented spent graphene oxide (SGO) for radioactive waste immobilization: A comparative study with spent ion-exchange resins
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DOI:10.1016/j.pnucene.2026.106492.png)
Abstract
En 中文
• Cemented spent graphene oxide (SGO) achieves 3 wt% waste loading and satisfies mechanical acceptance criteria. • Cemented SGO exhibits superior radionuclide retention compared with cemented spent ion-exchange resin (SIER). • Cs-137 shows higher mobility than Co-60, reflecting differences in sorption mechanisms and cesium solubility. • Effective diffusion coefficients confirm stronger immobilization of Co-60 in both cemented waste forms. • The proposed cemented SGO waste form demonstrates robust long-term performance under diffusion-controlled leaching conditions.
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