Comparative leaching studies of 60CO from spent radioactive ion — Exchange resin incorporated in cement

Plećasˇ, I.; Perić, A.; Glodić, S.; Kostadinović, A.

doi:10.1016/0008-8846(95)00016-x

Cited by 9 publications

(3 citation statements)

References 2 publications

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“…Fenton or Fenton-like process oxidation is mainly based on the attack of hydroxyl radicals (HOÁ) to the organic macromolecular, and the hydroxyl radicals were produced through the reaction of catalysts and H 2 O 2 , as in Eqs. (1)(2)(3)(4).…”

Section: Introductionmentioning

confidence: 99%

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Optimization of spent radioactive resins degradation by Fenton‐like oxidation using response surface methodology

Wan

Wang

2016

Env Prog and Sustain Energy

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The degradation of spent radioactive resin by Fenton‐like process with Cu2+ as catalyst was optimized using response surface methodology (RSM) based on Box–Behnken design (BBD) method. The influence of three independent variables like catalyst concentration, H2O2 dosage, and initial pH value on resin degradation was investigated. The weight loss percentage of resin was evaluated using the quadratic model. Analysis of variance showed that correlation coefficient (R2) of the model was 0.9786, providing a satisfactory approximation of quadratic model with the experimental data. Out of three factors, especially pH value had significant influence on the weight loss percentage of resin. The weight loss percentage increased as pH decreased from 2.25 to 0.75. The conditions for resin degradation were optimized as follows: pH = 0.75, H2O2 = 20 mL, and catalyst concentration was 0.25 M. The confirmation experiment carried out at optimal conditions using RSM. The weight loss percentage was 95.80%. The predicted weight loss percentage was 96.19%, indicating that RSM based on BBD was a reliable method to optimize the operational conditions for resin degradation by Fenton‐like process. Finally, the intermediates of resin degradation were analyzed by ion chromatograph and GC‐MS. © 2016 American Institute of Chemical Engineers Environ Prog, 35: 1590–1596, 2016

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Section: Introductionmentioning

confidence: 99%

“…Several technologies have been applied for direct and indirect treatment of the spent radioactive resins. The direct methods include cementation , bituminization , and plastic solidification . However, the solidified waste forms have high volume and weight which can be a problem for transportation, storage, and management.…”

Section: Introductionmentioning

confidence: 99%

Optimization of spent radioactive resins degradation by Fenton‐like oxidation using response surface methodology

Wan

Wang

2016

Env Prog and Sustain Energy

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“…They were leached in de-ionised water at 20°C and 50°C because temperature is one of the factors that may influence the diffusion process of the leaching behaviour. Several authors have studied the leaching behaviour of cemented forms containing irradiated resins by following the leaching of 60 Co from a spent ion exchange resin incorporated into two types of cement for 25 days [4], by recording the cumulative fractional radioactive nuclide ( 137 Cs) release as a function of leaching time (240 days) [5], by periodically collecting and analyzing water which contacted cementitious wasteforms in field and laboratory test conditions [6], by measuring the leaching rate of 60 Co and 137 Cs from different ion exchange resins (cationic and mix bead ion exchange resins) in cement-bentonite matrix after 245 days [7]. Fortin and Caron [8] have measured the average concentrations of ions in leachates based on a 16-month monitoring period of eight waste containers and the complexing capacity of leachates with radionuclides of interest (cadmium and cobalt).…”

Section: Introductionmentioning

confidence: 99%

AComDim as a multivariate tool to analyse experimental design application to γ-irradiated and leached ion exchange resins

Korifi

Amat

Rébufa

et al. 2015

Chemometrics and Intelligent Laboratory Systems

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International audienceLeaching MIR spectroscopy Ion exchange resin γ-Irradiations of ion exchange resins were carried out under various experimental conditions, selected using an experimental design, to simulate the ageing of such nuclear wastes. Those resins are a commercial mixed bed, constituted of 75 wt.% of a cationic resin and 25 wt.% of an anionic resin, and both are pure cationic and anionic resins. Then, irradiated samples were leached, at two different temperatures (20 °C and 50 °C). Solid matrices were characterized by a spectroscopic technique and spectral data were analysed by the ANOVA Common Dimensions (AComDim) method to detect and highlight influential factors and interactions. Four factors were studied (absorbed dose under irradiation, atmosphere during irradiation, dose rate, leaching temperature and resin type) with several levels for each. In a first study of the separate resins, the absorbed dose and the irradiation atmosphere appeared as the most influencing factors for the anionic resin. The leaching temperature was significant but only in interaction with other factors, while this parameter was significant for the cationic and mixed bed resins. In a global study of all the spectral data, the resin type appeared as the most influential factor for the radiolysis of resins

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Treatment of spent radioactive anionic exchange resins using Fenton-like oxidation process

Wan

Wang

2016

Chemical Engineering Journal

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Comparative leaching studies of 60CO from spent radioactive ion — Exchange resin incorporated in cement

Cited by 9 publications

References 2 publications

Optimization of spent radioactive resins degradation by Fenton‐like oxidation using response surface methodology

Optimization of spent radioactive resins degradation by Fenton‐like oxidation using response surface methodology

AComDim as a multivariate tool to analyse experimental design application to γ-irradiated and leached ion exchange resins

Treatment of spent radioactive anionic exchange resins using Fenton-like oxidation process

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