Immobilization of NPP evaporator bottom high salt-bearing liquid radioactive waste into struvite-based phosphate matrices

Kononenko, O. A.; Milyutin, V. V.; Makarenkov, V. I.; Kozlitin, E. A.

doi:10.1016/j.jhazmat.2021.125902

Cited by 20 publications

(4 citation statements)

References 40 publications

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“…The chemical reaction occurs between basic magnesia and an acid solution containing phosphates and, during this process, various components can be incorporated [12]. Struvite is indeed promising as a candidate compound for conditioning liquid radioactive waste from nuclear power plants [13]. The formation of this type of cement is too fast and very exothermic [14].…”

Section: Introductionmentioning

confidence: 99%

Study of Modified Magnesium Phosphate Cement for Fluoride Removal

Gharsallah,

Mallah,

Alsawi

et al. 2023

Materials

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In this study, we used a novel composite material based on magnesium phosphate cement (MPC) to explore the retention of fluoride from used water. Dead-burned magnesium oxide (MgO), ammonium dihydrogen phosphate (NH4H2PO4), and a few retarders were used to create this particular substance. Several studies have corroborated the performance of using aluminum in the capture of fluoride. From this perspective, we attempted to reinforce our matrix with different quantities of aluminum, which increased the resistance of the composite in water. The optimal conditions that were obtained were evaluated and scrutinized using a range of techniques, including scanning electron microscopy (SEM), X-ray diffraction (XRD), thermogravimetric analysis (TGA), Fourier transforms infrared spectroscopy (FTIR), and Brunauer–Emmett–Teller (BET). The adsorbents demonstrated a powerful ability to remove fluoride from contaminated water and the defluoridation capacity was evaluated at 4.84 mg/g. Equilibrium modeling was carried out, and the experimental data were expressed in accordance with the Langmuir, Freundlich, Temkin, and Dubinin–Radushkevich isotherms.

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Section: Introductionmentioning

confidence: 99%

Study of Modified Magnesium Phosphate Cement for Fluoride Removal

Gharsallah,

Mallah,

Alsawi

et al. 2023

Materials

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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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“…The chemical and radionuclide composition of a specific batch of liquid radioactive medium is determined by the conditions of its formation and is not the same even for the same-type NPPs after their mixing. However, it can be argued that the content of radionuclides in radwaste is six or more orders of magnitude less than that of ballast (nonradioactive) components [1][2][3]. Therefore, a reduction in the cost of radioactive waste processing can be achieved by excluding ballast components from the radwaste composition.…”

Section: Introductionmentioning

confidence: 99%

Minimization of radioactive waste volume from nuclear power plants using precipitation-membrane technologies

Vinnitskii

Chugunov

2022

BIO Web Conf.

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The purpose of this study is the development and experimental testing on simulation solutions of a precipitation-membrane method for fractionation of liquid radioactive waste and sorption post-treatment of the filtrate. The choice of processing method is based on the analysis of factors affecting the efficiency of ion-exchange purification of solutions; properties of complex compounds of polyvalent metals; characteristics of commercially available membrane elements and economic aspects of the preparation and disposal of radioactive waste. The basic idea is to use the internal properties of solutions to isolate polyvalent cations and acidoligands in the form of poorly soluble compounds in the volume of an inert polypropylene element, which will increase the efficiency of ion-exchange post-treatment and reduce the amount of waste. The architecture and operating parameters of the experimental setup are designed to provide favorable conditions for the formation in solution of complexes (ion pairs) of polycharged cations with acid ligands of various nature.

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Immobilization of NPP evaporator bottom high salt-bearing liquid radioactive waste into struvite-based phosphate matrices

Cited by 20 publications

References 40 publications

Study of Modified Magnesium Phosphate Cement for Fluoride Removal

Study of Modified Magnesium Phosphate Cement for Fluoride Removal

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

Minimization of radioactive waste volume from nuclear power plants using precipitation-membrane technologies

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