A simple and rapid technique for recovery of 99mTc from low specific activity (n,γ)99Mo based on solvent extraction and column chromatography

Chattopadhyay, Sankha; Das, Sujata Saha; Barua, Luna

doi:10.1016/j.apradiso.2009.07.024

Cited by 23 publications

(10 citation statements)

References 5 publications

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“…Methyl ethyl ketone (MEK) is the best for the extraction of 99m Tcpertechnetate in terms of high extraction yield, high radiation stability, and low boiling temperature [33,34]. The solvent extraction based 99m Tc generator systems recently developed are designed for an automated or semi-automated operation either on the established extraction process or on the improved extraction technologies [35,36]. In the present experiment, we have used similar chemical technique for the separation of 99m Tc from 99 Mo.…”

Section: Resultsmentioning

confidence: 98%

Preparation of 99Mo from the 100Mo(γ, n) reaction and chemical separation of 99mTc

Gopalakrishna¹,

Naik

Suryanarayana

et al. 2015

J Radioanal Nucl Chem

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The radionuclide 99 Mo has been prepared by 100 Mo(c, n) reaction using two types of natural molybdenum compound (molybdenum trioxide and zirconium molybdate gel) with the bremsstrahlung end-point energies of 10 and 15 MeV. After the equilibrium, 99m Tc was separated as NaTcO 4 from the irradiated samples using two different chemical procedures to examine the chemical yield. The separated Na[ 99m Tc]TcO 4 from the ZrMo gel has the 99Mo breakthrough of \10 -4 %, radiochemical purity[99 % as well as chemical impurities of Al, Mo and Zr \ 10 ppm. The estimation of 99 Mo and 99m Tc was done by using off-line c-ray spectrometric technique. The chemical yield of the separated 99m Tc from the dissolved molybdenum trioxide is 70.7-75.2 %, whereas in the undissolved zirconium molybdate gel, it is 19.1-43 %. The second method is preferable because it is user friendly in hospital radiopharmacy throughout the shelf-life.Keywords Medical isotope 99 Mo-9m Tc Á 100 Mo(c,n) reaction Á Molybdenum trioxide Á Zirconium molybdate gel Á Off-line c-ray spectrometric technique Á Chemical yield

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Section: Resultsmentioning

confidence: 98%

Preparation of 99Mo from the 100Mo(γ, n) reaction and chemical separation of 99mTc

Gopalakrishna¹,

Naik

Suryanarayana

et al. 2015

J Radioanal Nucl Chem

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“…Such low specific activity 99 Mo/ 99m Tc preparations require separation technologies different from the current commercial alumina columns as alumina has a capacity of only up to 20 mg/g molybdenum. Alternative technologies for separation, including solvent extraction, have been variously reviewed in literature [15][16][17][18][19][20][21][22]. MEK solvent extraction was described first by Gerlit in 1956 [23].…”

Section: Resultsmentioning

confidence: 99%

Processing and evaluation of linear accelerator-produced 99Mo/99mTc in Canada

Mangera

Ogbomo

Zriba

et al. 2015

J Radioanal Nucl Chem

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We are developing electron linear accelerator 100 Mo(c,n) 99 Mo technology as a replacement to nuclear reactor 235 U(n,f) 99 Mo production. We report irradiation of natural molybdenum disks (25 MeV, 10 kW) and 100 Moenriched disks (35 MeV, 2 kW), their dissolution and the extraction of 99m Tc-pertechnetate. Up to 6.2 GBq 99 Mo was produced, solvent extraction was performed at [90 % yields of 99m Tc, and quality control showed that a product with high radionuclidic and radiochemical purity could be obtained. Irradiated natural molybdenum products showed more impurities ( 91m Nb, 92m Nb, 95m Nb and 95 Nb) than enriched target material. Linear accelerator technology is feasible for production of quality 99 Mo/ 99m Tc, particularly when paired with 100 Mo-enriched targets.

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“…The choice of this extraction procedure relies on the high efficiency demonstrated on this kind of application by Chattopadhyay et al [30,31] and Martini et al [32,33]. Indeed, the selected affinity of pertechnetate for the organic solvent methylethylketon (MEK) allows a high pertechnetate yield extraction (greater than 90% [20]) from an aqueous alkaline phase in which molybdate and other by-products remain in solution.…”

Section: Resultsmentioning

confidence: 99%

14 MeV Neutrons for 99Mo/99mTc Production: Experiments, Simulations and Perspectives

et al. 2018

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Background: the gamma-emitting radionuclide Technetium-99m (99mTc) is still the workhorse of Single Photon Emission Computed Tomography (SPECT) as it is used worldwide for the diagnosis of a variety of phatological conditions. 99mTc is obtained from 99Mo/99mTc generators as pertechnetate ion, which is the ubiquitous starting material for the preparation of 99mTc radiopharmaceuticals. 99Mo in such generators is currently produced in nuclear fission reactors as a by-product of 235U fission. Here we investigated an alternative route for the production of 99Mo by irradiating a natural metallic molybdenum powder using a 14-MeV accelerator-driven neutron source. Methods: after irradiation, an efficient isolation and purification of the final 99mTc-pertechnetate was carried out by means of solvent extraction. Monte Carlo simulations allowed reliable predictions of 99Mo production rates for a newly designed 14-MeV neutron source (New Sorgentina Fusion Source). Results: in traceable metrological conditions, a level of radionuclidic purity consistent with accepted pharmaceutical quality standards, was achieved. Conclusions: we showed that this source, featuring a nominal neutron emission rate of about 1015 s−1, may potentially supply an appreciable fraction of the current 99Mo global demand. This study highlights that a robust and viable solution, alternative to nuclear fission reactors, can be accomplished to secure the long-term supply of 99Mo.

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A simple and rapid technique for recovery of 99mTc from low specific activity (n,γ)99Mo based on solvent extraction and column chromatography

Cited by 23 publications

References 5 publications

Preparation of 99Mo from the 100Mo(γ, n) reaction and chemical separation of 99mTc

Preparation of 99Mo from the 100Mo(γ, n) reaction and chemical separation of 99mTc

Processing and evaluation of linear accelerator-produced 99Mo/99mTc in Canada

14 MeV Neutrons for 99Mo/99mTc Production: Experiments, Simulations and Perspectives

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