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Response of soil bacteria to PUREX chemicals suggests biomarker utility and bioremediation potential
Chemicals involved in plutonium uranium reduction extraction (PUREX) can be released from nuclear reprocessing facilities and accumulate in the...
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Determination of concentration of formaldehyde in high level waste during the destruction of nitric acid in PUREX process
A simple titrimetric procedure has been developed for the determination of the concentration of formaldehyde present in nitric acid. The procedure is...
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Substantiation of the Practical Feasibility of the Modified Scheme of Purex Process with an Increased TBP Concentration Using Mathematical Modeling
AbstractIn order to expand the existing database on the extraction of SNF components, experimental data were obtained on the extraction of nitric...
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Extractive Recovery and Сoncentration of Palladium(II) from Simulated Nitrate–Nitrite PUREX Process Raffinate with 4-[(Hexylsulfanyl)methyl]-3,5-dimethyl-1-phenyl-1H-pyrazole
AbstractThe possibility of recovering and concentrating Pd(II) from simulated nitrate–nitrite PUREX process raffinate with a highly effective...
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Spectrophotometric determination of di-butyl phosphate in PUREX solvent using peroxo disulfate as oxidizing agent
A spectrophotometric method has been developed for the estimation of di-butyl phosphate present in a solution of TBP in n-DD. The quantitative...
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Comparison of Dynamic Tests of the Modified Purex Process Flowsheet Using 30 and 45% TBF in Isoparaffin
AbstractResults of centrifugal contactor rig trials of the flowsheet of the first solvent extraction cycle in protective glove boxes using simulated...
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Study of irradiation decomposition products of PUREX solvents on zirconium metal retention behavior
The metal retention behaviors of several simulated radiolysis products on zirconium metal were investigated, and it was found that acid phosphate...
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Solvent wash studies for the removal of di-butyl phosphate from spent solvent under simulated PUREX condition
Reprocessing of high plutonium content spent nuclear fuel from fast reactors results in the generation of lean organic solution containing...
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Mathematical modeling of the co-decontamination process in PUREX
A mathematical model of co-decontamination process (1A) containing U(VI), Pu(IV), Zr(IV), and Ru(III) was developed with a high-performance Iteration...
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Effect of vaporization on thermal stability of model PUREX-process raffinates
The aqueous phase formed during the regeneration of the irradiated extractant contains organic products that degrade into gases upon heating and...
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Partitioning of the High Level Radioactive Waste from the Purex Process by 40% TBF in Isoparaffin Using Magnesium Nitrate as a Salting-out Agent
AbstractCentrifugal contactor rig trials of the partitioning flowsheet were carried out using simulated and real high level waste solutions obtained...
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Electrolytic and ozone aided destruction of oxalate ions in plutonium oxalate supernatant of the PUREX process: A comparative study
The article describes an efficient and straight forward method for the destruction of oxalate ions in the plutonium oxalate supernatant stream...
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The development status of PUREX process for nuclear fuel reprocessing from an insight from PATENTS
The PUREX process has been one of the most successful methods to reprocess spent nuclear fuel for several decades, and further enhancements have...
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Neptunium redox speciation and determination of its total concentration in dissolved fuel simulant solutions by spectrophotometry
Two new approaches to measure Np concentration in dissolved used nuclear fuel simulant (aqueous feed for PUREX process) by spectrophotometry are...
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Kinetics of dissolution of simulated (U–Ce) MOX fuel pellet in nitric acid
In the present study, the dissolution kinetics of simulated urania, ceria MOX fuel pellets in nitric acid under PUREX process condition has been...
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Precise determination of plutonium in nuclear fuel process samples
A REDOX-based analytical method was developed for determining the plutonium concentration. In this method, plutonium was oxidized to the +6-oxidation...
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Structure and aggregation behavior of pertechnetate/perrhenate in organic phase in the extraction by tributyl phosphate
The extraction of pertechnetate (TcO 4 − ) and perrhenate (ReO 4 − ) by tributyl phosphate (TBP) has been extensively studied, but the structure of the...
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Selective separation of Pu(IV) and U(VI) with bisdiglycolamde ligands: solvent extraction and DFT calculations
The extractant tri-n-butyl phosphate (TBP) was used for the separation of Pu(IV) and U(VI) in the PUREX process, which brings phosphorus pollution...
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Solvent Extraction Systems for Separation of An(III) and Ln(III): Overview of Static and Dynamic Tests
AbstractThe management of high-level radioactive waste generated during the reprocessing of spent nuclear fuel in the PUREX process is among of the...
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Nitric Acid Corrosion Issues of Spent Fuel Nuclear Fuel Reprocessing Plants Materials
The degradation of reprocessing materials to nitric acid corrosion in aqueous spent fuel nuclear reprocessing plants is an unwanted and serious...