Liquid-liquid extraction of Hf(IV) from nitric acid with dibutylsulfoxide in cyclohexane

Khan, Muhammad Haleem; Ali, Akbar

doi:10.1524/ract.2002.90.5_2002.297

Cited by 6 publications

(2 citation statements)

References 23 publications

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“…Amberlite XAD-16 resin functionalized with nitrosonaphthol was [183] used for the adsorption of Ni(II) and Cu(II) [158] and amberlite XAD-4 resin impregnated with dibenzoylmethane (DBM) was employed in flow injection for the determination of U(VI) from aqueous solution of pH 5.5 [159], the same impregnated with N-benzoylphenylhydroxylamine was utilised in flow injection for the determination of Th(IV) from aqueous solution of pH 4.5 [160]. di-n-butyl sulfoxide (DBSO) was used for the separation of Hf(IV) [161] and Th(IV) [162] by solvent extraction. PAN was used for the separation of Hg [111], IB, IIB and IIIA-VA elements [163] by solvent extraction and U(VI) by adsorption [164].…”

Section: Separation Studiesmentioning

confidence: 99%

Development of radiochemistry in Pakistan – 1960 to 2010

et al. 2012

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Development of radiochemistry / Uranium and thorium chemistry / Nuclear reaction cross section / Radioisotope and radiopharmaceutical production / Neutron activation analysis / Separation studies / PINSTECHSummary. With the inception of Pakistan Atomic Energy Commission (PAEC) in 1956, peaceful uses of atomic energy commenced for the benefit of scientific community as well as masses of Pakistan. Radiochemistry played a vital role right from the beginning. The research and development in this field accelerated soon after the criticality of the first research reactor named as Pakistan Research Reactor (PARR-1) at the Pakistan Institute of Nuclear Science and Technology (PINSTECH), Islamabad. The first radioisotope produced at PARR-1 for application in nuclear medicine was 131 I. Later on, many other radioisotopes were prepared and radiopharmaceuticals were synthesised for their use in industry and hospitals. Besides providing pure radioactive tracers for nuclear medicine, radiochemistry also enhanced the detection limit of impurities at all stages of nuclear fuel cycle for power generation. In 1983, research in the field of nuclear data measurement began. The main aim was to identify suitable conditions for the production of radionuclides for cancer diagnostics, treatment and therapy. With the establishment of a second research reactor (PARR-2) at PINSTECH, research in neutron activation analysis, radioisotope production and separation studies gained more momentum and many research articles were published. Solvent extraction, adsorption and ion-exchange were the main routes of separation in those studies. Separation of heavy metals and treatment of waste generated in a nuclear power plant are other important aspects related to environmental restoration and nuclear waste management, where radiochemistry is required. In future, work in radiochemistry will be continued on similar lines to develop novel radiopharmaceuticals, identify indigenous schemes for nuclear waste management and work out intelligent procedures for material characterization for benefit to mankind, especially the people of Pakistan.

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Section: Separation Studiesmentioning

confidence: 99%

Development of radiochemistry in Pakistan – 1960 to 2010

et al. 2012

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“…Until now, hafnium extraction has been performed in several ways such as liquid-liquid extraction [30], hydrogen plasma arc melting [31], resins [32,33] and hollow fiber renewal liquid membrane technique [24]. So far, various carriers such as Ionquest 801 [34], benzyl alcohol [35], din-butyl sulfoxide (DBSO) [36], Cyanex 921, Cyanex 923, Cyanex 925 [37], DEHPA, Cyanex 272, TBP, Primene JTM, Alamine 336 and Aliquat 336 [38], TOP, DOS, D2EHPA [39], PC 88A, Lix 63 [40] have been used to extract hafnium ions. However, to the best of our knowledge, the extraction of the Hf metal via the emulsion liquid membrane using the Cyanex 572 carrier has not been reported so far.…”

Section: Introductionmentioning

confidence: 99%

Investigation of experimental results and D-optimal design of hafnium ion extraction from aqueous system using emulsion liquid membrane technique

2020

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Hafnium metal is used in a wide range of industries such as microprocessor manufacturing, nuclear reactors and special alloys due to its physical, chemical and radiation properties. Emulsion liquid membrane (ELM) is an effective and efficient alternative for heavy metal separation compared to conventional methods due to high selectivity, energy-saving, high mass transfer and low operating capital. In this study, Cyanex 572 as a carrier, Span 85 as a surfactant, hydrochloric acid as an internal phase and kerosene as a diluent were used. In the first part of the study, the stability of the emulsions was investigated. The most stable emulsions were obtained by adding PIB polymer (3% w/v), Span 85 surfactant (3% w/v) and stirring for 15 min. In the second part, the separation of hafnium metal ions from aqueous solutions was investigated using ELM technique. The highest separation was obtained at 4% (v/v) as carrier concentration, 4% (w/v) as surfactant concentration, the membrane-to-feed volume ratio of 20/100 and W/O/W emulsion stirring rate and time equal to 400 rpm and 5 min, respectively. Moreover, to optimize the factors influencing the tests, the design of experiment (DOE) was performed using D-optimal method via Design Expert 10 software. Based on DOE results, the maximum extraction (> 99%) was achieved when the carrier concentration, the surfactant concentration, W/O/W emulsion stirring time, W/O/W emulsion stirring rate and emulsion volume/feed phase ratio were 4.49% v/v, 3.90% w/v, 11.49 min, 310.54 rpm and 2:1, respectively.

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