Immobilization of Simulated Borate Radioactive Waste Solution in Cement-Poly(methylmethacrylate) Composite: Mechanical and Chemical Characterizations

Saleh, Hosam M.; Shatta, H. A.

doi:10.1155/2013/749505

Cited by 5 publications

(4 citation statements)

References 8 publications

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“…Several studies discussed that, with reaction of the boric acid and calcium hydroxide (produced during the cementations), calcium borate were produced, which is insoluble; it acts as a barrier and retards the diffusion of elements. 39 In the case of B, the lower leached fraction was associated with the highest compressive strengths in the case of 50 OXY-B. However, the leachability of B correlates with the obtained mechanical data.…”

Section: Compressive Strength Test Resultsmentioning

confidence: 99%

Characterization of Simulated Liquid Radioactive Waste in a New Type of Cement Mixture

et al. 2022

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There is still a safety challenge for the long-term stabilization of nuclear waste. Due to its affordable price and easy manufacturing, cement is one of the most promising materials to immobilize a large volume of low- and intermediate-level radioactive liquid waste. To investigate the effect of borate on the cementation of radioactive evaporator concentrates and to provide more data for solidification formula optimization, simulated liquid waste in various concentrations was prepared. Different borate concentrations were solidified in ordinary Portland cement (OPC) and in two new cement compositions with water resistance and boron-binding additives. The chemical and mechanical properties were investigated for nine cementitious samples, together with three compositions in three concentrations. The leaching rate of the boron is lower in the case of a high strength cement mixture. The compressive strengths of the solidified waste correlate with the leaching rates of the boron. The leaching rates of Ca were changed with the cement composition and even with the boron concentrations; first, they were lower in the initial OPC in the case of the same boron concentration (50 g/L); second, they were lower at a higher boron concentration (250 g/L) for the OXY-B composition. The simulated liquid waste with higher boron concentrations solidified with newly developed cement composition (OXY-B) shows a homogeneous boron distribution in the volume of the cement cylinder both before and after leaching. The formulas of OXY and OXY-B developed in this application were effective for cementation of the simulated borate evaporator concentrates.

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Section: Compressive Strength Test Resultsmentioning

confidence: 99%

Characterization of Simulated Liquid Radioactive Waste in a New Type of Cement Mixture

et al. 2022

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“…The positive relationship between the total leached boron and the initial boron concentration (Fig. 5) is due to the more availability and the subsequent higher possibility of boroncontaining minerals getting dissolved from the cementitious host structure [93]. Nevertheless, high leachability can lead to lower chemical stability and durability for the solidified specimens, which is a critical parameter in the long-term disposal of cementitious waste.…”

Section: Boron Leachability Versus Initial Boron Concentrationmentioning

confidence: 99%

“…4) shows a continuous growth together with the increase of the initial boron concentration in the specimens. This phenomenon may be related to the porosity increase as the initial boron concentration grows (discussed in "Solid samples mineralogy versus running leaching tests" section ) and the constraint of cementitious matrices to hold other solid materials or precipitating boron-bearing minerals from boric acid solutions [20,58,93].…”

Section: Boron Leachability Versus Initial Boron Concentrationmentioning

confidence: 99%

The geochemical role of B-10 enriched boric acid in cemented liquid radioactive wastes

Rostamiparsa

Tolnai

Czömpöly

et al. 2023

J Radioanal Nucl Chem

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Boric acid is a significant radioactive waste generated during the operation of nuclear power plants. Cementitious materials have been widely studied for the immobilization of boric acid. The generally used natural boric acid has been replaced by enriched boric acid for geochemical reasons and are expected to have varied behaviors in cementitious matrices. Results showed that simulated enriched/natural boric acid liquid wastes mostly contain boron in $${\mathrm{B}(\mathrm{OH})}_{4}^{-}$$ B ( OH ) 4 - and $${{\mathrm{B}}_{5}{\mathrm{O}}_{6}(\mathrm{OH})}_{4}^{-}$$ B 5 O 6 ( OH ) 4 - ionic forms, but the mass ratio of these species is higher in enriched boric acid solutions. In function with the concentration of enriched/natural boric acid, the solidified cementitious materials show different mineralogy.

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“…Cement-waste fiber composite was produced due to the incorporation of waste fibers in cementitious materials and used in radioactive waste immobilization [6][7][8][9]. Polymers also were impregnated with cement to increase the durability and reduce the porosity of cement, producing favorable composite suitable for many applications and resistive to various aggressive conditions [10][11][12][13][14][15]. Natural additives such as clay were mixed progressively with cement to treat the retardation property of organic solvent with cement [16,17].…”

Section: Cement Compositesmentioning

confidence: 99%

Introductory Chapter: Properties and Applications of Cement- Based Materials

Saleh¹,

Rahman²

2018

Cement Based Materials

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Cement-based materials have been used to support human civilizations many decades ago. With the increasing advancement of human activities, these materials were modified to maintain their roles in our lives. The main function of cement is to act as hydraulic binder, which increases the bond between fragmented particles, so it can enable their use in different fields. The resulted material will have different physical and mechanical properties from the initial materials. These changed properties are attributed to the exothermic hydration reactions that are initiated upon mixing the binder with water. The liberated localized heat will lead irreversible rearrangement of water molecules within the framework microstructure [1-3]. Ordinary Portland Cement (OPC) is the most widely used cement. It is prepared by crushing, milling, and mixing calcium, iron, silica, alumina, and sulfate sources with certain amounts. Then, hydraulic cement is passed to the kiln to produce clinker, which is subsequently cooled and pulverized. Portland cement is categorized into eight subgroups according to the ASTM C150, namely normal (type I), moderate sulfate resistance (type II), high early strength (type III), low heat of hydration (type IV), high sulfate resistance (type V), normal, moderate sulfate resistance, and high early resistance with air entraining (types IA, IIA, IIIA), respectively [4]. There are four principal unhydrated phases present in all OPC types, namely tricalcium silicate (Ca 3 SiO 5), dicalcium silicate (Ca 2 SiO 4), tricalcium aluminate (Ca 3 Al 2 O 5), and calcium aluminoferrite (Ca 4 Al n Fe 2-n O 7). The formula of each of these minerals can be broken down into the basic calcium, silicon, aluminum, and iron oxides (Table 1). Cement chemists use abbreviated nomenclature based on oxides of various elements to indicate chemical formulae of relevant species, that is, C = CaO, S = SiO 2 ,A=A l 2 O 3 , and F = Fe 2 O 3. Hence, traditional cement nomenclature abbreviates each oxide as shown in Table 1 [1].

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Immobilization of Simulated Borate Radioactive Waste Solution in Cement-Poly(methylmethacrylate) Composite: Mechanical and Chemical Characterizations

Cited by 5 publications

References 8 publications

Characterization of Simulated Liquid Radioactive Waste in a New Type of Cement Mixture

Characterization of Simulated Liquid Radioactive Waste in a New Type of Cement Mixture

The geochemical role of B-10 enriched boric acid in cemented liquid radioactive wastes

Introductory Chapter: Properties and Applications of Cement- Based Materials

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