Cyclotron Production of 99mTc using 100Mo2C targets

Richards, Vernal N.; Mebrahtu, Efrem; Lapi, Suzanne E.

doi:10.1016/j.nucmedbio.2013.06.005

Cited by 17 publications

(15 citation statements)

References 23 publications

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“…These include the use of accelerated-proton, -electron, ordeuteron. The primary accelerated charged particles are used to produce energetic secondary particles (photon/neutron) which then interact with the target material, producing 99 Mo [9]. Production of 99m Tc using electron LINAC is reported to be technically simple and economically and ecologically feasible [10].…”

Section: Mmentioning

confidence: 99%

Development of 99Mo/99mTc Generator System for Production of Medical Radionuclide 99mTc using a Neutron-activated 99Mo and Zirconium Based Material (ZBM) as its Adsorbent

et al. 2016

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Section: Mmentioning

confidence: 99%

Development of 99Mo/99mTc Generator System for Production of Medical Radionuclide 99mTc using a Neutron-activated 99Mo and Zirconium Based Material (ZBM) as its Adsorbent

et al. 2016

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“…In 2009-2010 both reactors have experienced long scheduled/ unscheduled shutdowns, thus causing a temporary shortage of 99 Mo and 99m Tc on the radionuclides' international market. Such an event has prompted the international scientific community to investigate new production routes for these vital radionuclides [4][5][6][7][8].…”

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confidence: 99%

Experimental cross section evaluation for innovative 99Mo production via the (α,n) reaction on 96Zr target

Pupillo

Esposito

Gambaccini

et al. 2014

J Radioanal Nucl Chem

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The high-specific activity 99Mo accelerator-based production, via the (α,n) reaction on 96Zr-enriched target, has been investigated in the present work. The excitation function measurement has been performed in the energy range 8–34 MeV at the ARRONAX facility, using the well-known stacked foils technique on natural zirconium as target. A general good agreement in the cross section trend has been observed, once compared to former measurements. A different (i.e. higher) peak value and a shift of about 2 MeV towards larger energies have however been found. Assuming a fully enriched 96Zr target irradiated by an α-beam at suitable energy (E = 25 MeV), the 99Mo production yield has thus been estimated. At last the alternative production routes, based on the 96Zr(α,n)99Mo and 100Mo(p,x)99Mo/99mTc reactions, are compared

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“…Thermo-chromatography, a sublimation method as described by Vleck et al [23] was employed in this separation as previously reported for the separation of 99m Tc from 100 Mo 2 C [21]. Fig.…”

Section: Target Processingmentioning

confidence: 99%

“…186 WC is not soluble in hot base as is 186 WO 3 , or in other common laboratory chemicals, thus precluding the use of a wet chemical method for post bombardment processing. Similar to the processing of 186 W metal [18,20], and 100 Mo 2 C [21], thermo-chromatography can be used in the processing of 186 WC. 186 WC oxidizes in air above 500°C to 186 WO 3 enabling the facile release of volatile 186g Re species leaving behind 186 WO 3 [20] making it available for recycling.…”

Section: Introductionmentioning

confidence: 99%

Production and separation of 186gRe from proton bombardment of 186WC

Richards

Rath

Lapi

2015

Nuclear Medicine and Biology

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A proof of concept study was undertaken where non-carrier added (186 g)Re was produced from the cyclotron bombardment of (186)WC. (186)WC was carbo-thermally generated from a novel precursor synthesized from (186)WO3, aqueous ammonia and hexamethyltetramine. The inherent high electrical and thermal conductivity of this material, coupled with its high melting point, made it an ideal candidate for proton bombardment for production of (186)Re. An18 μA irradiation for 3h and processing via thermo-chromatography, (186)WC yielded 0.93 mCi of (186 g)Re which corresponds to 89% of the calculated theoretical yields. The radiochemical purity of the desired (186 g)Re species was found to be between 95 and 97% with small contaminants of (186)ReO2. The radiochemistry utility of the product was investigated using S-benzoyl-MAG3, and 100% complexation was achieved with stability being maintained for 96 h. The re-oxidation of (186)WC back to(186)WO3 by oxygen in the thermo-chromatography method of processing ensured that the starting material was regenerated and recovered from the process in 94-98% yield.

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Cyclotron Production of 99mTc using 100Mo2C targets

Cited by 17 publications

References 23 publications

Development of <sup>99</sup>Mo/<sup>99m</sup>Tc Generator System for Production of Medical Radionuclide <sup>99m</sup>Tc using a Neutron-activated <sup>99</sup>Mo and Zirconium Based Material (ZBM) as its Adsorbent

Development of <sup>99</sup>Mo/<sup>99m</sup>Tc Generator System for Production of Medical Radionuclide <sup>99m</sup>Tc using a Neutron-activated <sup>99</sup>Mo and Zirconium Based Material (ZBM) as its Adsorbent

Experimental cross section evaluation for innovative 99Mo production via the (α,n) reaction on 96Zr target

Production and separation of 186gRe from proton bombardment of 186WC

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