Separation and purification of radiomolybdenum from a fission product mixture using silver-coated carbon granules

Arino, Hirofumi; Kramer, H.H.

doi:10.1016/0020-708x(78)90030-3

Cited by 19 publications

(3 citation statements)

References 6 publications

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“…Alumina is positively charged in an acid medium and so can adsorb negatively charged molybdate ion or polymers of molybdate ion as shown in (4) and (5). (Fig.…”

Section: First Purification Of "Mo By Alumina Adsorptionmentioning

confidence: 99%

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Process Study on the Separation of ⁹⁹Mo from Irradiated Natural Uranium Dioxide

et al. 1989

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A chemical process for the separation and purification of fission product "Mo by the irradiation of natural U0 2 targets has been developed. The major separation steps include: (1) Extraction of "Mo with 5% D2EHPA (Di-2-Ethylhexyl Phosphoric Acid)/ kerosene from a nitric acid solution (2) Removal of H 2 0 2 in a dilute acid medium with a platinum catalyst (3) Initial purification of "Mo by alumina adsorption, and (4) Final purification of "Mo by calcium phosphate hydroxide adsorption. Variables affecting on the chemical yield and purity of "Mo in each process step were examined in batch studies. A full-scale synthetic solution experiment with the established optimum process conditions was carried out in a hot cell. It is estimated that 20 to 70 curies of "Mo can be obtained by irradiating about 400 grams of natural UO, target at TRR (Taiwan Research Reactor) with a neutron flux of 5 X 10' 3 n/cm 2 /sec. The calculated specific activity of the "Mo product solution is 6 X 10 2 to 3 X 10 3 Ci/g and its estimated radionuclide purity and other quality assay were extremely satisfactory. The experimental results indicated that this separated high specific activity of "Mo is suitable for the preparation of " m Tc generator for nuclear medical applications.

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“…Alumina is positively charged in an acid medium and so can adsorb negatively charged molybdate ion or polymers of molybdate ion as shown in (4) and (5). (Fig.…”

Section: First Purification Of "Mo By Alumina Adsorptionmentioning

confidence: 99%

“…SAMEH used a combination of chelex-100 ion exchange separation and alumina adsorption [4]. A high specific activity "Mo was also obtained by ARINO [5] which utilized silver coated charcoal as an adsorbent. The separation of "Mo with α-benzoin oxime precipitation was studied by SIVARAKIAHNAN [6].…”

Section: Introductionmentioning

confidence: 99%

Process Study on the Separation of ⁹⁹Mo from Irradiated Natural Uranium Dioxide

et al. 1989

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“…Chromatographic column techniques are generally preferred for the separation of fission-"Mo than solvent extraction [14][15][16][17][18] and precipitation [19 -22]. In this respect, "Mo was separated from different fission solutions by adsorption on alumina [23,24], silver-coated alumina [10,25], silver-coated charcoal [26,27] and organic exchangers [12,28]. The obtained "Mo eluates are usually seriously contaminated with the radionuclides 131,132^ 132 Τβ) 95^ 95^ 103 Ru> ^ ^ 2γ> 29].…”

Section: Introductionmentioning

confidence: 99%

Separation of Fission ⁹⁹Mo on Charcoal Columns Impregnated with Tin(IV) Chloride for Use in Preparation of ^99mTc Generators

El-Absy

1991

Radiochimica Acta

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Fission molybdenum-99 / Separat: Charcoal impregnated with tin(IV) Alumina / Technetium-99m generator SummaryA radiochemical procedure to separate mCi quantities of carrierfree "Mo from irradiated uranium targets is described. "Mo(VI) was quantitatively adsorbed onto small columns of charcoal impregnated with tin(IV) chloride from fission products solution in 0.25 Μ HCl. From a single adsorption-desorption cycle, >86% "Mo was recovered in 10 cm 3 0.75 Μ NaOH eluent with > 99.6% radionuclidic purity. A product purity of >99.98% "Mo was obtained by recycling on a new column. The suitability of the produced "Mo for preparation of "Mo/ " m Tc generators was verified by adsorption on alumina columns and " m Tc elution with saline solution.

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Determination of Trace Molybdenum in Biological Matrices by Neutron Activation Analysis

Yeh

1984

J Chinese Chemical Soc

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Based on consecutive extractions using bismuth diethyldithiocarbamate and thallium diethyldithiocarbamate as reagents, molybdenum was selectively and highly enriched from biological matrices, and then subjected to neutron activation analysis. Most of interfering elements, e.g., Na, K, Br, P, Fe, U, etc. were simultaneouly removed and the preconcentrated samples always showed only the r rays from molybdenum after neutron bombardment. Thus, molybdenum in the biological matrices could be accurately determined.

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Separation and purification of radiomolybdenum from a fission product mixture using silver-coated carbon granules

Cited by 19 publications

References 6 publications

Process Study on the Separation of ⁹⁹Mo from Irradiated Natural Uranium Dioxide

Process Study on the Separation of ⁹⁹Mo from Irradiated Natural Uranium Dioxide

Separation of Fission ⁹⁹Mo on Charcoal Columns Impregnated with Tin(IV) Chloride for Use in Preparation of ^99mTc Generators

Determination of Trace Molybdenum in Biological Matrices by Neutron Activation Analysis

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Separation and purification of radiomolybdenum from a fission product mixture using silver-coated carbon granules

Cited by 19 publications

References 6 publications

Process Study on the Separation of 99Mo from Irradiated Natural Uranium Dioxide

Process Study on the Separation of 99Mo from Irradiated Natural Uranium Dioxide

Separation of Fission 99Mo on Charcoal Columns Impregnated with Tin(IV) Chloride for Use in Preparation of 99mTc Generators

Determination of Trace Molybdenum in Biological Matrices by Neutron Activation Analysis

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Process Study on the Separation of ⁹⁹Mo from Irradiated Natural Uranium Dioxide

Process Study on the Separation of ⁹⁹Mo from Irradiated Natural Uranium Dioxide

Separation of Fission ⁹⁹Mo on Charcoal Columns Impregnated with Tin(IV) Chloride for Use in Preparation of ^99mTc Generators