99Mo/99mTc separation: An assessment of technology options

Dash, Ashutosh; Knapp, F. F.; Pillai, M.R.A.

doi:10.1016/j.nucmedbio.2012.10.005

Cited by 70 publications

(45 citation statements)

References 107 publications

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“…The purification of 99m Tc-pertechnetate from molybdenum at various specific activities was reviewed in a recent publication (29). Several methods are not applicable to cyclotron-produced 99m Tc because of the quantity of nonradioactive molybdenum present in the target dissolution mixture.…”

Section: Discussionmentioning

confidence: 99%

Implementation of Multi-Curie Production of ^99mTc by Conventional Medical Cyclotrons

et al. 2014

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99m Tc is currently produced by an aging fleet of nuclear reactors, which require enriched uranium and generate nuclear waste. We report the development of a comprehensive solution to produce 99m Tc in sufficient quantities to supply a large urban area using a single medical cyclotron. Methods: A new target system was designed for 99m Tc production. Target plates made of tantalum were coated with a layer of 100 Mo by electrophoretic deposition followed by high-temperature sintering. The targets were irradiated with 18-MeV protons for up to 6 h, using a medical cyclotron. The targets were automatically retrieved and dissolved in 30% H 2 O 2 . 99m Tc was purified by solid-phase extraction or biphasic exchange chromatography. Results: Between 1.04 and 1.5 g of 100 Mo were deposited on the tantalum plates. After high-temperature sintering, the 100 Mo formed a hard, adherent layer that bonded well with the backing surface. The targets were irradiated for 1-6.9 h at 20-240 μA of proton beam current, producing up to 348 GBq (9.4 Ci) of 99m Tc. The resulting pertechnetate passed all standard quality control procedures and could be used to reconstitute typical anionic, cationic, and neutral technetium radiopharmaceutical kits. Conclusion: The direct production of 99m Tc via proton bombardment of 100 Mo can be practically achieved in high yields using conventional medical cyclotrons. With some modifications of existing cyclotron infrastructure, this approach can be used to implement a decentralized medical isotope production model. This method eliminates the need for enriched uranium and the radioactive waste associated with the processing of uranium targets.

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Section: Discussionmentioning

confidence: 99%

Implementation of Multi-Curie Production of ^99mTc by Conventional Medical Cyclotrons

et al. 2014

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“…Recovering the irradiated dry powder and simple dissolution in sodium hydroxide solution provides sodium ( 99 Mo) molybdate, the source of 99m Tc. 99m Tc can be separated using any one of the established methods (8). Solvent extraction using methyl ethyl ketone is effective and simple, and cost-effective automated modules can be developed for the preparation of high concentrations of no-carrier-added 99m Tc activity (9).…”

Section: Diversified Processing Facilities For Reactor-produced Low-smentioning

confidence: 99%

Diversification of ⁹⁹Mo/^99mTc Separation: Non–Fission Reactor Production of ⁹⁹Mo as a Strategy for Enhancing ^99mTc Availability

Pillai¹,

Dash

Knapp

2015

J Nucl Med

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This paper discusses the benefits of obtaining 99m Tc from non-fission reactor-produced low-specific-activity 99 Mo. This scenario is based on establishing a diversified chain of facilities for the distribution of 99m Tc separated from reactor-produced 99 Mo by (n,γ) activation of natural or enriched Mo. Such facilities have expected lower investments than required for the proposed chain of cyclotrons for the production of 99m Tc. Facilities can receive and process reactorirradiated Mo targets then used for extraction of 99m Tc over a period of 2 wk, with 3 extractions on the same day. Estimates suggest that a center receiving 1.

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“…But we also wanted enable access to 99m Tc without requiring substantial infrastructure changes within the healthcare community. Alternative 99m Tc purification methods have recently been reviewed [37]. We have tested several methods applicable to recovering 99m Tc from a bulk level of Mo, most of which exploit the favorable free energy of hydration of TcO 4 − over other components of the target mixture [38].…”

Section: Pertechnetate Purificationmentioning

confidence: 99%

Direct Production of 99mTc via 100Mo(p,2n) on Small Medical Cyclotrons

Schaffer

Bénard

Bernstein³

et al. 2015

Physics Procedia

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From the efforts of a number of Canadian institutions and private industry collaborations, direct production of 99m Tc using medical cyclotrons has recently been advanced from a 1970's academic exercise to a commercial, economically viable solution for regional production. Using GE PETtrace 880 machines our team has established preliminary saturated yields of 2.7 GBq/μA, translating to approximately 174 GBq after a 6 hour irradiation. The team is in the process of assessing the accuracy and reliability of this production value with a goal of optimizing yields by up to 50%.

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99Mo/99mTc separation: An assessment of technology options

Cited by 70 publications

References 107 publications

Implementation of Multi-Curie Production of ^99mTc by Conventional Medical Cyclotrons

Implementation of Multi-Curie Production of ^99mTc by Conventional Medical Cyclotrons

Diversification of ⁹⁹Mo/^99mTc Separation: Non–Fission Reactor Production of ⁹⁹Mo as a Strategy for Enhancing ^99mTc Availability

Direct Production of 99mTc via 100Mo(p,2n) on Small Medical Cyclotrons

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99Mo/99mTc separation: An assessment of technology options

Cited by 70 publications

References 107 publications

Implementation of Multi-Curie Production of 99mTc by Conventional Medical Cyclotrons

Implementation of Multi-Curie Production of 99mTc by Conventional Medical Cyclotrons

Diversification of 99Mo/99mTc Separation: Non–Fission Reactor Production of 99Mo as a Strategy for Enhancing 99mTc Availability

Direct Production of 99mTc via 100Mo(p,2n) on Small Medical Cyclotrons

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Implementation of Multi-Curie Production of ^99mTc by Conventional Medical Cyclotrons

Implementation of Multi-Curie Production of ^99mTc by Conventional Medical Cyclotrons

Diversification of ⁹⁹Mo/^99mTc Separation: Non–Fission Reactor Production of ⁹⁹Mo as a Strategy for Enhancing ^99mTc Availability