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Production of 125I from neutron irradiation of natural Xe gas and a wet distillation process for radiopharmaceutical applications / P. V. Joshi in Industrial & engineering chemistry research, Vol. 51 N° 25 (Juin 2012) 

Public ISBD [article]  in Industrial & engineering chemistry research > Vol. 51 N° 25 (Juin 2012) . - pp. 8575-8582 Titre : Production of 125I from neutron irradiation of natural Xe gas and a wet distillation process for radiopharmaceutical applications Type de document : texte imprimé Auteurs : P. V. Joshi, Auteur ; K. C. Jagadeesan, Auteur ; R. B. Manolkar, Auteur Année de publication : 2012 Article en page(s) : pp. 8575-8582 Note générale : Industrial chemistry Langues : Anglais (eng) Mots-clés : Distillation  Production Résumé : In this article, we describe a simple and facile approach for the production of 125I from the neutron-irradiated natural Xe using wet chemical distillation. First, we outline the design of the irradiation container, its fabrication, cryogenic loading of the gaseous Xe target into the irradiation container, and hermetic sealing of the irradiation container. Quality-assurance tests of the irradiation containers were performed to ensure their safety during neutron irradiation. In light of the implicit need to obtain 125I activity with minimum126I radionuclidic contamination, the irradiation time, neutron flux, and target cooling time were judiciously optimized. A thorough optimization of esperimental parameters of distillation was carried out to obtain the optimal yield of 125I having the desired purity. In each batch, typically 4 g of natural xenon gas was irradiated in the BARC Dhruva reactor for 15 days with a thermal neutron flux of approximately 5 × 1013 cm―2 s―1. After irradiation, the targets were left to decay for typically ∼50 days to reduce the 126I contamination. Several batches of 125I were successfully produced using the developed procedure at a level of ∼18.5 GBq (500 mCi) 125I per batch. The 125I quality in terms of radionuclidic purity, radiochemical purity, and radioactive concentration was evaluated and found to be acceptable for radiolabeling studies. This reported method currently has been adapted for the routine production of 125I to meet local needs. ISSN : 0888-5885 En ligne : http://cat.inist.fr/?aModele=afficheN&cpsidt=26066783 [article] Production of 125I from neutron irradiation of natural Xe gas and a wet distillation process for radiopharmaceutical applications [texte imprimé] / P. V. Joshi, Auteur ; K. C. Jagadeesan, Auteur ; R. B. Manolkar, Auteur . - 2012 . - pp. 8575-8582. Industrial chemistry Langues : Anglais (eng) in Industrial & engineering chemistry research > Vol. 51 N° 25 (Juin 2012) . - pp. 8575-8582 Mots-clés : Distillation  Production Résumé : In this article, we describe a simple and facile approach for the production of 125I from the neutron-irradiated natural Xe using wet chemical distillation. First, we outline the design of the irradiation container, its fabrication, cryogenic loading of the gaseous Xe target into the irradiation container, and hermetic sealing of the irradiation container. Quality-assurance tests of the irradiation containers were performed to ensure their safety during neutron irradiation. In light of the implicit need to obtain 125I activity with minimum126I radionuclidic contamination, the irradiation time, neutron flux, and target cooling time were judiciously optimized. A thorough optimization of esperimental parameters of distillation was carried out to obtain the optimal yield of 125I having the desired purity. In each batch, typically 4 g of natural xenon gas was irradiated in the BARC Dhruva reactor for 15 days with a thermal neutron flux of approximately 5 × 1013 cm―2 s―1. After irradiation, the targets were left to decay for typically ∼50 days to reduce the 126I contamination. Several batches of 125I were successfully produced using the developed procedure at a level of ∼18.5 GBq (500 mCi) 125I per batch. The 125I quality in terms of radionuclidic purity, radiochemical purity, and radioactive concentration was evaluated and found to be acceptable for radiolabeling studies. This reported method currently has been adapted for the routine production of 125I to meet local needs. ISSN : 0888-5885 En ligne : http://cat.inist.fr/?aModele=afficheN&cpsidt=26066783