4.7 Article

Immobilization of cesium and iodine into Cs3Bi2I9 perovskite-silica composites and core-shell waste forms with high waste loadings and chemical durability

Journal

JOURNAL OF HAZARDOUS MATERIALS
Volume 401, Issue -, Pages -

Publisher

ELSEVIER
DOI: 10.1016/j.jhazmat.2020.123279

Keywords

Pervoskite; Fission product; Silica; Waste form; Sparking plasma sintering

Funding

  1. Center for Performance and Design of Nuclear Waste Forms and Containers (WastePD), an Energy Frontier Research Center (EFRC) - U.S. Department of Energy, Office of Science, Basic Energy Sciences [DE-SC0016584]
  2. DOE [DE-AC05-76RL01830]

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Two strategies were explored to form Cs3Bi2I9-silica composites and a core-shell structure in order to improve chemical durability of waste form materials meanwhile maintaining high waste loadings. Cs and I were incongruently released from waste form matrices due to the formation of a BiOI alteration layer acting as a passivation layer to reduce the release of radionuclides. This work highlights a robust way to immobilize highly mobile radionuclides with high waste loadings through encapsulation into durable matrices and a surface passivating mechanism.
Cs3Bi2I9, a defect perovskite derivative, is a potential host phase to immobilize iodine and cesium with high waste loadings. In this work, two strategies were explored to form Cs3Bi2I9-silica composites and a core-shell structure in order to improve chemical durability of waste form materials meanwhile maintaining high waste loadings. Cs3Bi2I9 loadings as high as 70 wt.% were incorporated into a silica matrix to form silica-ceramic composites, and 20 wt.% Cs3Bi2I9 was encapsulated into silica to form a core-shell structure by low temperature spark plasma sintering. Chemical durability of the composite and core-shell waste forms was evaluated by semidynamic leaching experiments, and Cs and I were incongruently released from waste form matrices. A BiOI alteration layer formed, acting as a passivation layer to reduce the release of radionuclides. The long-term iodine release rate was low (30 mg m(-2) day 1) for the 70 wt.% Cs3Bi2I9-silica composite leached in deionized water at 90 degrees C, which can be further reduced to 5 x 10(-3) mg m(-2) day(-1) for the 20 wt.% core-shell structure. This work highlights a robust way to immobilize the highly mobile radionuclides with high waste loadings through encapsulation into durable matrices and a surface passivating mechanism that can greatly reduce the elemental transport from waste form materials and significantly enhance their chemical durability.

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