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We have developed chelator-free copper-64-incorporated iron oxide (IO) nanoparticle (NPs) which have both magnetic and radioactive properties being applied to positron emission tomography (PET)-magnetic resonance imaging (MRI). We have found that the IO nanoparticles composed of radioactive isotope 64Cu may act as a contrast agent being a diagnostic tool for PET as well as a good T2 MRI nanoprobe due to their good r2/r1 ratio. Furthermore, we demonstrate that the 64Cu incorporation at the core of core-shell-structured IO NPs exhibits a good in vivo stability, giving us an insightful strategy for the design of a contrast agent for the PET-MRI system.
RESUMEN
PURPOSE: The potential of P-32 ophthalmic applicator irradiation after pterygium excision has been demonstrated as an alternative to Sr∕Y-90 irradiation. This study aimed to provide the clinical dosimetry for this new applicator. METHODS: The prototype of a cylindrical P-32 applicator was fabricated according to the Monte Carlo (MC)-based design study. At a nominal activity of 6 mCi (0.22 GBq), the absorbed dose rate at the front surface (i.e., reference dose rate) was measured by using an extrapolation ionization chamber (EC). The radiochromic film (RCF) was also used to measure the reference dose, axial depth dose distributions and transaxial dose profiles at various depths in water. RESULTS: The reference dose rate was 3.89 ± 0.14 cGy∕s for EC and 3.84 ± 0.25 cGy∕s for RCF. The depth dose rate was reduced approximately by an order of magnitude for every 2 mm depth in water. Measured depth doses in depths of 0.5-2.5 mm agreed with Monte Carlo data within ±3%. Due to nonuniform absorption of P-32 into an absorbent disk, the dose profiles were not symmetric and decreased more rapidly toward the periphery than those predicted by the MC. The authors confirmed no leakage of P-32 activities and negligible exposure rate around the hand grip of the applicator. CONCLUSIONS: The P-32 applicator can deliver therapeutic doses to the surface of the conjunctiva, while sparing the lens better than Sr∕Y-90 applicators. The doses at any points from the P-32 applicator could be calculated by using the measured dosimetry data. They also confirmed no leakage of the source, reliable integrity of the applicator, and negligible exposure level around the hand grip of the applicator. However, due to a possibility of nonuniform distributions of P-32 in an absorbent disk, measuring dose profiles as well as the reference dose rate for every new applicator would be recommended.
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Ojo , Radiometría/instrumentación , Método de Montecarlo , Radioisótopos de Fósforo , Factores de TiempoRESUMEN
Removing radioactive iodine from solutions containing fission products is essential for nuclear facility decontamination, radioactive waste treatment, and medical isotope production. For example, the production of high-purity fission 99Mo by irradiation of 235U with neutrons involves the removal of iodine from an alkaline solution of the irradiated target (which contains numerous fission products and a large quantity of aluminate ions) using silver-based materials or anion-exchange resins. To be practically applicable, the utilized iodine adsorbent should exhibit a decontamination factor of at least 200. Herein, the separation of radioactive iodine from alkaline solutions was achieved using alumina doped with silver nanoparticles (Ag NPs). Ag NPs have a larger surface area than Ag powder/wires and can thus adsorb iodine more effectively and economically, whereas alumina is a suitable inert support that does not adsorb 99Mo and is stable under basic conditions. The developed adsorbents with less impurities achieved iodine removal and recovery efficiencies of 99.7 and 62%, respectively, thus being useful for the production of 131I, a useful medical isotope.
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A separation study using a (176)Yb target for the preparation of nca (177)Lu, which is a beta-emitting nuclide used not only in radioimmunotherapy applications but also in the treatment of various lesions, has been performed. A material having a better selectivity and separation efficiency for Lu than Yb was developed, and the separation conditions of (177)Lu were derived using this from a neutron irradiated (176)Yb target. The separation material was an organo-ceramic hybrid material containing a phosphate group. Adsorption behavior was determined through batch experiments, and (177)Lu separation from the Yb target was evaluated through column experiments. The Yb target, with a 99.72% in (176)Yb, was irradiated in the irradiation hole of HANARO, which has a thermal neutron flux of 1.6E+14ncm(-2)s(-1). The batch experiments revealed that the organo-ceramic hybrid material (Sol-POS) had a separation factor of 1.6 at 0.5M HCl. Separation was performed through extraction chromatography using a 5mg enriched Yb target, and the separation yield of the NCA (177)Lu was about 78%. If the amount of Yb target is increased to produce curies level (177)Lu, additional purification will be needed.
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Lutecio/aislamiento & purificación , Radioisótopos/aislamiento & purificación , Radiofármacos/aislamiento & purificación , Adsorción , Quelantes , Cromatografía/métodos , Humanos , Lutecio/uso terapéutico , Neutrones , Radioisótopos/uso terapéutico , Radiofármacos/uso terapéutico , República de Corea , Tecnología Radiológica/instrumentación , Tecnología Radiológica/métodos , Iterbio/efectos de la radiaciónRESUMEN
Organo-ceramic hybrid materials have been developed as the separation media for a (90)Sr/(90)Y generator system. Currently available (90)Y is generally extracted from a mother solution by a solvent extraction or a successive column operation. Both processes are successfully applied to produce (90)Y with a high quality standard. However, such processes are highly dependent on what kind of extracting materials are employed. Hence, some of the previously developed technologies are not adequate for a (90)Y production because of a waste generation or leaching of radiolytic end-products from the extracting materials. In this study, high performance organo-ceramic hybrid materials have been applied for the extraction of (90)Y. The hybrid materials have properties of both a ceramic and a solvent extractant by molecularly implanting the extracting molecules on to the ceramic surfaces. In this study, organo-phosphorus functionalized hybrid materials are synthesized and tested as the separation media for the (90)Y/(90)Sr generator system. An adsorptive extraction with a small Sep-Pak type column can recover more than 92% of (90)Y with a contamination ratio of (90)Sr/(90)Y=1.2x10(-5) from the mother solution and 70% with 5x10(-7).
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Cromatografía/métodos , Dióxido de Silicio/química , Radioisótopos de Estroncio/aislamiento & purificación , Radioisótopos de Itrio/aislamiento & purificación , Adsorción , Cerámica , Impresión Molecular , Compuestos Organofosforados , Generadores de RadionúclidosRESUMEN
A synthetic alumina functionalized with a sulfate moiety has been developed as the column material of (99)Mo/(99m)Tc and (188)W/(188)Re generators. This material is synthesized by a sol-gel processing. In order to characterize the adsorbent for the (188)W/(188)Re separation, both batch and column contact experiments were conducted. As a result of the experiments, it is found that the maximum capacity of the adsorbent for tungsten is higher than 450mg/g. Hence it is possible to produce approximately 3Ci (188)W/(188)Re generator with only 1g of the adsorbent from (188)W solutions supplied from ORNL, USA or RIAR, Russia. A demonstration study was conducted to show the performance of an (188)W/(188)Re generator column. In this study, 1Ci of (188)W purchased from RIAR, Russia, is loaded on a 0.9cm ID column packed with 0.7g of the adsorbent. Elution of (188)Re is performed every 4-7 days by using the saline solution for more than three months. Nearly 100% of tungsten is loaded by passing 5ml of the (188)W solution (pH=8) through the dry packed column at a 1ml/min flow rate. Elution efficiency of (188)Re is 70-90% by using 5ml of the saline solution. The ratio of (188)W/(188)Re in the eluted solution is 0.002-0.003%. When a Sep-Pak containing 0.26g of acid alumina is installed as a tandem column, the ratio is decreased to less than 10(-3)%. Thin layer chromatography for the eluted (188)Re solution shows 100% radiochemical purity. Also, alumina content in the eluted solution shows less than 10ppm. Through this study, the performance of this adsorbent was successfully demonstrated. By using the developed adsorbent, minimization of the generator column and consequently the volume of eluant could be possible while maintaining the quality of (188)Re just as much as that available in the market.