2023
DOI: 10.1016/j.jnucmat.2022.154194
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Structure, crystallization behavior and chemical stability analysis of Nd3+-basaltic glasses for immobilizing simulated trivalent actinides

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Cited by 4 publications
(1 citation statement)
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“…The disposal of high-level radioactive waste in China comprises immobilization in an inert substrate and subsequent deep geological disposal in a geological repository [ 8 , 9 , 10 ]. Glass solidification is currently the only industrially available technology for treating HLW, and borosilicate glass is considered to be a good glass solidification substrate due to its good chemical durability and irradiation resistance [ 7 , 11 , 12 ]. All elements in HLW can be accommodated in borosilicate, but the low solubility of some long-lived radioactive actinides, such as Np, Pu, Cm, and Am, in borosilicate glass can limit the development of glass curing technology.…”
Section: Introductionmentioning
confidence: 99%
“…The disposal of high-level radioactive waste in China comprises immobilization in an inert substrate and subsequent deep geological disposal in a geological repository [ 8 , 9 , 10 ]. Glass solidification is currently the only industrially available technology for treating HLW, and borosilicate glass is considered to be a good glass solidification substrate due to its good chemical durability and irradiation resistance [ 7 , 11 , 12 ]. All elements in HLW can be accommodated in borosilicate, but the low solubility of some long-lived radioactive actinides, such as Np, Pu, Cm, and Am, in borosilicate glass can limit the development of glass curing technology.…”
Section: Introductionmentioning
confidence: 99%