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Дмитриев, С. А.; Lifanov, F. A.; Savkin, A.E.; Lashchenov, C. M.

doi:10.1023/a:1011338231351

Cited by 9 publications

(1 citation statement)

References 2 publications

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“…Concentrates are high salt solutions with typical specific activity concentrations in the range 10 6 -10 8 Bq/L [31]. Major contaminants in the evaporator concentrates are fission products such as 137 Cs, 60 Co, 54 Mn, borates (NaBO 2 and Na 2 B 4 O 7 ), nitrates (NaNO 3 , KNO 3 ), hydroxides (NaOH and KOH), and some organic compounds, i.e., oxalates [31][32][33]. In general, alkali and alkaline fission products, e.g., 85 Sr, 137 Cs, are characterized by their respective high solubility in the cementitious matrices [34,35].…”

Section: General Characteristics Of Concentrates and Their Problematic Naturementioning

confidence: 99%

Toward Sustainable Cementitious Radioactive Waste Forms: Immobilization of Problematic Operational Wastes

Rahman

Ojovan

2021

Sustainability

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Developing effective radioactive waste management practices is essential for ensuring the sustainability of the nuclear industry. The immobilization of radioactive wastes is one of the main activities conducted during the management of these wastes; it aims to produce a durable waste form that has sustainable performance over long periods of time. In this work, the challenges that face the design of durable cementitious waste forms are addressed for problematic operational wastes. In this respect, the problematic characteristics of evaporator concentrates, spent ion exchangers, and organic liquid wastes are overviewed, and the factors that affect the durability of their cementitious waste forms are identified. A summary of potential conventional and innovative cementitious matrices is presented by reviewing the cementation practices in national programs and recent research devoted to developing durable matrices. Finally, a guide to optimize the mix design of these waste forms was proposed that includes the selection of the testing procedure, factors that affect the waste form performance, and the optimization technique. This guide was presented with special focus on leaching tests, which are a means to test the stabilization performance of nuclear waste forms.

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