Utilization of bentonite and zeolite in cementation of dry radioactive evaporator concentrate

Plećaš, I.; Dimović, Slavko; Smiciklas, I.

doi:10.1016/j.pnucene.2005.12.001

Cited by 26 publications

(8 citation statements)

References 21 publications

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“…The radionuclides transport can be inhibited by incorporation of some sorption materials in to the concrete mixture. For that reason natural clays or synthetic alternatives [5,6,7,8] were successfully used.…”

Section: Introductionmentioning

confidence: 99%

Pore structure and hygric properties of composite materials for radionuclide protection barriers

et al. 2019

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Many practical applications of concrete require adjustment of its properties. If concrete is used as casing for radioactive waste deposits, its main purpose is to mitigate radionuclide release and the mix design must conform to this requirement. In this article bentonite as a material with great sorption capacity is used as a concrete component. The main issue is to assess durability of designed mixtures. Therefore, the pore structure and hygric properties are investigated. The experimental results show that bentonite utilization in concrete mixtures leads to a significant growth of pore amount in the range of 0.01 to 1 μm and increase of water transport ability.

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Section: Introductionmentioning

confidence: 99%

Pore structure and hygric properties of composite materials for radionuclide protection barriers

et al. 2019

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“…A radiation protection and a mitigation of a radionuclide release belong among the most important ones [5,6], but this is a problematic issue to be addressed. The transport of radionuclides can be successfully inhibited by some sorption materials, for example in the form of natural clays or synthetic alternatives [6,7,8]. In this article, an admixture of bentonite is employed.…”

Section: Introductionmentioning

confidence: 99%

Mechanical properties of concrete for radioactive waste repositories

et al. 2019

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Concrete casing for radioactive repositories have to meet many strict requirements. One of the most important is a radiation protection and a radionuclide inhabitation. Bentonite, with a great sorption capacity, seems to be a suitable material for this purpose. Therefore, the main aim of this study was to assess an impact of the bentonite utilization as a component in concrete mixtures. For this reason, basic physical properties and mechanical parameters of concretes containing different amount of bentonite were determined. Bentonite applications led to the open porosity growth, while the matrix densities were not influenced. Regarding the mechanical parameters, the compressive strengths as well as the flexural strengths were significantly deteriorated by the bentonite application. Despite the presented negative effect, the obtained results seems to prove a possible applicability of a lower percentage of bentonite in concrete structures not as a cement replacement, but just as a component.

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“…The results showed that the effect of zeolite was most significant, followed by blast-furnace slag, fly ash, and silica fume in sequence [16]. Influence of bentonite and zeolite as natural sorbents on immobilization of evaporator concentrates in the cement matrix has been studied, and reduction of leaching rate is determined by the increasing amount of bentonite and zeolite, as ordinary sorption materials for 137 Cs, 60 Co, and 85 Sr [17].…”

Section: Introductionmentioning

confidence: 99%

Immobilization of radioactive borate liquid waste using natural diatomite

Osmanlıoğlu

2015

Desalination and Water Treatment

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In this article, influence of diatomite as a natural adsorbent in immobilization of radioactive borate liquid waste in the cement-diatomite matrix was investigated. Cylindrical concrete mixtures were prepared with different amounts of diatomite additives at three different w/c values. Mechanical strength tests were carried out to determine the uniaxial compressive strength of the samples. A new dynamic column type leaching tests were applied to the solidified waste forms, and leach rates of 137 Cs and 60 Co were determined according to different diatomite additives. The experimental results indicated that the increasing of the diatomite additive amounts resulted high isolation performance of the solidified waste form. However, the results revealed that mechanical strength decreases with increasing borate diatomite amount. Results show that 9% amount of natural diatomite is effective as an admixture of the cementation process for achieving long-term stability of solidified borate waste. Optimum strength and leach values were determined as 11.5 MPa with leaching rates of 7.5 × 10 −4 and 3.2 × 10 −5 cm/d for 137 Cs and 60 Co, respectively.

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Utilization of bentonite and zeolite in cementation of dry radioactive evaporator concentrate

Cited by 26 publications

References 21 publications

Pore structure and hygric properties of composite materials for radionuclide protection barriers

Pore structure and hygric properties of composite materials for radionuclide protection barriers

Mechanical properties of concrete for radioactive waste repositories

Immobilization of radioactive borate liquid waste using natural diatomite

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