Performance of Cement for Immobilizing Strontium Waste in Saline Environment

Putero, Susetyo Hario; Rosita, Widya

doi:10.4236/msa.2013.412a002

Cited by 2 publications

(1 citation statement)

References 3 publications

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“…Increasing concentrations of strontium ( 67.6, 70.2 and 71,6 ppm) were added to the GO solution and then mixed with cement. The concentrations used were chosen in a range close to the maximum solubility limit of the strontium in cement [14]. To realize 1 cm 3 cubic specimens was used OPC CEMII/BLL 32.5R.…”

Section: Methodsmentioning

confidence: 99%

Nanoreinforced concrete composites for possible nuclear waste confinement a preliminary study

Mancini,

Gattia,

Girardi

et al. 2023

EPJ Web Conf.

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Cementitious materials are the most abundant building materials even nowadays. Similarly, in the nuclear industry, concrete is the most used material for the confinement of radioactive waste, it has favorable properties, both chemical and physical, making it a desirable matrix for the encapsulation of radioactive and toxic wastes. Cemented wastes are preferred for the storage of a large varieties of fission products, such as low and intermediate level radioactive waste e.g., β—emitter 90Sr. Anyway, because of the intrinsic fragility of ordinary Portland Cement (OPC) a lot of efforts have been spent to enhance his mechanical resistance. Graphene Oxide (GO) represent an opportunity to overcome this problem. In fact, there is much evidence that GO can influence the toughness and the strength of the cement composites by regulating the morphology of the cement hydration products. 90Sr, the main strontium isotope in radioactive waste, is a by-product of the fission of uranium and plutonium in nuclear reactors. In this study we investigate the effects of strontium on mechanical properties of cement (OPC) and GO-reinforced cement. Different samples have been prepared with fixed concentration of GO. It has been observed that small quantities of GO, significantly [1] increases the compression strength of cement composites. The addition of Sr (65.0, 67.6 and 70.2 ppm) resulted in an increase of the compressive strength of 6.78%, 3.02% and 0.70% for those samples respectively, in comparison to OPC. Compression strength in samples of OPC with GO remained quite constant even in presence of Sr.

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Section: Methodsmentioning

confidence: 99%

Nanoreinforced concrete composites for possible nuclear waste confinement a preliminary study

Mancini,

Gattia,

Girardi

et al. 2023

EPJ Web Conf.

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Cellulose degradation products and high ionic strength enhance the retardation of strontium in hydrated cement paste

Hinchliff¹,

Felipe-Sotelo²,

Drury³

et al. 2022

Front. Nucl. Eng.

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The present concept for the disposal of some low- and all intermediate-level radioactive waste in the United Kingdom involves grouting with cement in steel drums and placement in a geological facility. The vaults would then be backfilled with low strength, high porosity cement-based materials designed to promote a pervasive, alkaline environment in which many of the radioactive species present are sparingly soluble. This work investigates the interaction of strontium with such a backfill under both diffusive and advective conditions given the potential significance of the fission product 90Sr. An important characteristic of the United Kingdom waste inventory is the abundance of organic compounds, including cellulosic materials; consequently, the experiments were repeated with products of alkaline cellulose degradation. Additional experiments were performed at high ionic strength simulating anticipated changes in the salinity of the groundwater. The effective diffusivity (De) of strontium in the absence of the organic compounds ranged between 5.5 × 10−11 and 8.5 × 10−11 m2 s−1, with a distribution coefficient (Rd) of between 2.8 × 10−3 and 3.1 × 10−3 m3 kg−1. The presence of organic compounds and/or an increase of ionic strength enhanced the retardation of strontium. The results indicate that the retention of strontium by hydrated cement paste occurs via a reversible ion exchange mechanism rather than mineralisation and is promoted by decalcification of the calcium silicate hydrate phases.

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Performance of Cement for Immobilizing Strontium Waste in Saline Environment

Cited by 2 publications

References 3 publications

Nanoreinforced concrete composites for possible nuclear waste confinement a preliminary study

Nanoreinforced concrete composites for possible nuclear waste confinement a preliminary study

Cellulose degradation products and high ionic strength enhance the retardation of strontium in hydrated cement paste

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