A computerized compact module for separation of 99mTc-radionuclide from molybdenum

Chattopadhyay, Sankha; Barua, Luna; De, Anirban; Das, Sujata Saha; Kuniyil, Remashan; Bhaskar, P.; Pal, Sarbajit; Sarkar, Suman; Das, Manab Kumar

doi:10.1016/j.apradiso.2012.07.013

Cited by 20 publications

(16 citation statements)

References 9 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…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

View full text Add to dashboard Cite

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.

show abstract

Section: Resultsmentioning

confidence: 99%

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

et al. 2018

View full text Add to dashboard Cite

show abstract

“…All of the accelerator-based nonfission approaches rely on highly enriched 100 Mo target. While the 99% enrichment 100 Mo is sufficient for all accelerator-based 99 Mo productions, the direct production of 99m Tc may require enrichments exceeding >99.5% due to the possible side reactions which generate long-lived technetium and molybdenum isotopes because these impure radionuclides would cause an unnecessary radiation dose burden to the patient and the waste disposal issues as well. The SA of 99 Mo produced from the accelerators is too low for use in existing commercial 99m Tc generator systems that use alumina columns.…”

Section: Low Specific Activity 99 Mo: Current Issues Of Production Anmentioning

confidence: 99%

TcGenerator Development: Up-to-DateTcRecovery Technologies for Increasing the Effectiveness of
Le¹
2014
Science and Technology of Nuclear Installations
16
0
8
0
View full text Add to dashboard Cite

A review on theMosources available today and on theTcgenerators developed up to date for increasing the effectiveness ofMoutilisation is performed in the format of detailed description of the features and technical performance of the technological groups of theMoproduction andTcrecovery. The latest results of the endeavour in this field are also surveyed in regard of the technical solution for overcoming the shortage ofMosupply. The technological topics are grouped and discussed in a way to reflect the similarity in the technological process of each group. The following groups are included in this review which are high specific activityMo: the current issues of production, the efforts of more effective utilisation, and the high specific activityMo-basedTcgenerator andTcconcentration units; low specific activityMo: theMoproduction based on neutron capture and accelerators and the direct production ofTcand the methods of increasing the specific activity ofMousing Szilard-Chalmers reaction and high electric power isotopic separator; up-to-date technologies ofTcrecovery from low specific activityMo: the solvent extraction-basedTcgenerator, the sublimation methods forMo/Tcseparation, the electrochemical method forTcrecovery, and the column chromatographic methods forTcrecovery. Besides the traditionalTc-generator systems, the integratedTcgenerator systems (Tcgenerator column combined with postelution purification/concentration unit) are discussed with the format of process diagram and picture of real generator systems. These systems are the technetium selective sorbent column-based generators, the high Mo-loading capacity column-based integratedTcgenerator systems which include the saline-eluted generator systems, and the nonsaline aqueous and organic solvent eluent-eluted generator systems using high Mo-loading capacity molybdategel and recently developed sorbent columns.Tcconcentration methods used in theTcrecovery from low specific activityMoare also discussed with detailed process diagrams which are surveyed in two groups forTcconcentration from the saline and nonsalineTc-eluates. The evaluation methods for the performance ofTc-recovery/concentration process and for theTc-elution capability versus Mo-loading capacity of generator column produced using low specific activityMosource are briefly reported. Together with the theoretical aspects ofTc/Moand sorbent chemistry, these evaluation/assessment processes will be useful for any further development in the field of theTcrecovery andMo/Tcgenerator production.

show abstract

“…Several methods have been successfully developed to separate high-quality 99m Tc from 99 Mo of low-specific activity by using any methods of chromatography, 21) sublimation, 22) and solvent extraction, 23) without using the alumina cow. Among the methods, the sublimation method is based on a different volatility of technetium heptoxide (Tc 2 O 7 ) and molybdenum trioxide (MoO 3 ); 99m Tc produced in MoO 3 volatilizes at a temperature lower than that of the sublimation of MoO 3 , which is 790 C. In fact, we successfully used the sublimation method, as briefly discussed below.…”

Section: Recovery Of 99m Tc From An Irradiated 100 Mo Samplementioning

confidence: 99%

Generation of Radioisotopes with Accelerator Neutrons by Deuterons

et al. 2013

View full text Add to dashboard Cite

A new system proposed for the generation of radioisotopes with accelerator neutrons by deuterons (GRAND) is described by mainly discussing the production of 99 Mo used for nuclear medicine diagnosis. A prototype facility of this system consists of a cyclotron to produce intense accelerator neutrons from the nat C(d,n) reaction with 40 MeV 2 mA deuteron beams, and a sublimation system to separate 99m Tc from an irradiated 100 MoO 3 sample. About 8.1 TBq/week of 99 Mo is produced by repeating irradiation on an enriched 100 Mo sample (251 g) with accelerator neutrons for two days three times. It meets about 10% of the 99 Mo demand in Japan. The characteristic feature of the system lies in its capability to reliably produce a wide variety of high-quality, carrier-free, carrier-added radioisotopes with a minimum level of radioactive waste without using uranium. The system is compact in size, and easy to operate; therefore it could be used worldwide to produce radioisotopes for medical, research, and industrial applications.

show abstract

A computerized compact module for separation of 99mTc-radionuclide from molybdenum

Cited by 20 publications

References 9 publications

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

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

TcGenerator Development: Up-to-DateTcRecovery Technologies for Increasing the Effectiveness of
Le¹
2014
Science and Technology of Nuclear Installations
16
0
8
0
View full text Add to dashboard Cite

Generation of Radioisotopes with Accelerator Neutrons by Deuterons

Contact Info

Product

Resources

About

A computerized compact module for separation of 99mTc-radionuclide from molybdenum

Cited by 20 publications

References 9 publications

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

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

TcGenerator Development: Up-to-DateTcRecovery Technologies for Increasing the Effectiveness ofLe1 2014Science and Technology of Nuclear Installations16080View full textAdd to dashboardCite

Generation of Radioisotopes with Accelerator Neutrons by Deuterons

Contact Info

Product

Resources

About

TcGenerator Development: Up-to-DateTcRecovery Technologies for Increasing the Effectiveness of
Le¹
2014
Science and Technology of Nuclear Installations
16
0
8
0
View full text Add to dashboard Cite