Optimization of Flowsheet for Scrubbing of Ruthenium during the Reprocessing of Fast Reactor Spent Fuels

Natarajan, R.; Dhamodharan, K.; Sharma, Pradeep Kumar; Pugazhendi, S.; Vijayakumar, V.; Pandey, N. K.; Rao, R. V. Subba

doi:10.1080/01496395.2013.807828

Cited by 14 publications

(4 citation statements)

References 9 publications

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“…ruthenium extraction is significantly lower when Clconcentration increases, which is in agreement with literature data. [17] Distribution data obtained without HCl are similar to those reported in reference [18] which confirm that the use of 106 Ru from spent fuel treatment is the best way to reproduce ruthenium behaviour in reprocessing process. This method was thus used for the whole distribution experiments performed in this part.…”

Section: Batch Experiments From a Genuine Solutionsupporting

confidence: 84%

“…[21] The model fits correctly the decrease in ruthenium extraction with uranium loading but slightly overestimates ruthenium distribution ratio at high uranium saturation. : Experimental (♦) and calculated (-) ruthenium distribution ratios versus nitric acid concentration in aqueous phase for H2O/HNO3/RuNO(NO3)3/TBP/TPH system at T=298.15 K. ◊: Natarajan's work [18] Figure 7: Ruthenium speciation diagram for the H2O/HNO3/RuNO(NO3)3/TBP/TPH system at T=298.15 K.…”

Section: Modelling Resultsmentioning

confidence: 99%

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Experimental and modelling study of ruthenium extraction with tri-n-butylphosphate in the purex process

Moeyaert

Miguirditchian

Masson

et al. 2017

Chemical Engineering Science

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Ruthenium extraction by tri-n-butylphosphate (TBP) from nitric acid was studied and modelled in the conditions of the PUREX process. Experimental distribution ratios obtained for water, nitric acid and ruthenium were described with a physicochemical model based on the application of the mass action law on each extraction equilibrium and by taking into account deviations from thermodynamic ideal behaviour both in aqueous and organic phase using Mikulin and Sergievskii-Dannus equations. The best agreement between experimental and calculated ruthenium extraction isotherms was obtained by considering the formation of two complexes and in organic phase. This model was then used to simulate ruthenium behaviour in a counter-current PUREX hot test performed in mixer-settlers. Highlight  Extraction of ruthenium from nitric acid media by TBP/TPH was studied at lab-scale  A thermodynamic model based on Mikulin equation and Sergievskii-Dannus model was developped  Good agreement between experimental and calculated distribution ratios was obtained  Mathematical model was tested successfully during a counter-current PUREX hot test performed in mixer-settlers

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Section: Batch Experiments From a Genuine Solutionsupporting

confidence: 84%

Section: Modelling Resultsmentioning

confidence: 99%

Experimental and modelling study of ruthenium extraction with tri-n-butylphosphate in the purex process

Moeyaert

Miguirditchian

Masson

et al. 2017

Chemical Engineering Science

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“…Mixed carbide fuel containing 70% plutonium and 30% uranium is being used as the driver fuel in the Fast Breeder Test Reactor (FBTR) at Kalpakkam, India. The spent fuels discharged after irradiation up to 155 GWD/T is being reprocessed in Compact Reprocessing facility for Advanced fuel in Lead shielded cell (CORAL) using Purex process [1][2][3][4][5] . In this process, irradiated fuel pin is chopped into small pieces and this fuel matrix is dissolved in 11 M nitric acid under reflux condition.…”

Section: Introductionmentioning

confidence: 99%

Precise determination of plutonium in nuclear fuel process samples

et al. 2022

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“…A high acid flow sheet condition is essential to obtain an improved decontamination factor with respect to ruthenium in the case of spent fuels of fast reactors owing to its high yield in fast neutron spectrum and high burn up. 5 Therefore, the acidity of the feed solution before the solvent-extraction process plays an important role in obtaining the desired decontamination factor of U and Pu with respect to the fission products and minimizing the loss of plutonium in raffinate stream. To prevent precipitation of the solution containing hydrolysable ions during storage, an optimum value of acidity is required.…”

Section: Introductionmentioning

confidence: 99%

Sequential Determination of Free Acidity and Plutonium Concentration in the Dissolver Solution of Fast-Breeder Reactor Spent Fuels in a Single Aliquot

Dhamodharan

Pius

2016

ANAL. SCI.

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A simple potentiometric method for determining the free acidity without complexation in the presence of hydrolysable metal ions and sequentially determining the plutonium concentration by a direct spectrophotometric method using a single aliquot was developed. Interference from the major fission products, which are susceptible to hydrolysis at lower acidities, had been investigated in the free acidity measurement. This method is applicable for determining the free acidity over a wide range of nitric acid concentrations as well as the plutonium concentration in the irradiated fuel solution prior to solvent extraction. Since no complexing agent is introduced during the measurement of the free acidity, the purification step is eliminated during the plutonium estimation, and the resultant analytical waste is free from corrosive chemicals and any complexing agent. Hence, uranium and plutonium can be easily recovered from analytical waste by the conventional solvent extraction method. The error involved in determining the free acidity and plutonium is within ±1% and thus this method is superior to the complexation method for routine analysis of plant samples and is also amenable for remote analysis.

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Optimization of Flowsheet for Scrubbing of Ruthenium during the Reprocessing of Fast Reactor Spent Fuels

Cited by 14 publications

References 9 publications

Experimental and modelling study of ruthenium extraction with tri-n-butylphosphate in the purex process

Experimental and modelling study of ruthenium extraction with tri-n-butylphosphate in the purex process

Precise determination of plutonium in nuclear fuel process samples

Sequential Determination of Free Acidity and Plutonium Concentration in the Dissolver Solution of Fast-Breeder Reactor Spent Fuels in a Single Aliquot

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