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dc.contributor.authorÖzdoğan, Hasan
dc.contributor.authorŞekerci, Mert
dc.contributor.authorCinoğlu Karaca, Merve
dc.contributor.authorOkutan, Murat
dc.contributor.authorDemir, Bayram
dc.contributor.authorKaplan, Abdullah
dc.date.accessioned2023-03-09T09:16:13Z
dc.date.available2023-03-09T09:16:13Z
dc.date.issued2022en_US
dc.identifier.citationÖzdoğan, H., Şekerci, M., Cinoğlu Karaca, M., Okutan, M., Demir, B. ve Kaplan, A. (2022). An investigation on production routes of U-230 radioisotope used in targeted alpha therapy by different level density models. Moscow University Physics Bulletin, 77(6), 878-885. https://dx.doi.org/10.3103/S0027134922060170en_US
dc.identifier.issn0027-1349
dc.identifier.issn1934-8460
dc.identifier.urihttps://dx.doi.org/10.3103/S0027134922060170
dc.identifier.urihttps://hdl.handle.net/20.500.12511/10591
dc.description.abstractTargeted alpha therapy (TAT) is an attractive therapeutic option in patients with multiple micrometastases. It offers many advantages, including easy administration, the ability to treat multiple lesions simultaneously and the possibility of combination with other therapeutic approaches for improved efficacy. The aim of this study is to investigate the optimum production route of U-230, which is a promising TAT isotope, in cyclotrons. For this, Pa-231(p, 2n)U-230, Pa-231(d, 3n)U-230, Th-232(p, 3n)Pa-230, and Th-232(d, 4n)Pa-230, reactions cross-sections, total activity and reaction yield have been calculated by using different level density models of TALYS 1.95 code. It is possible to produce an U-230 activity of 53.491 mCi via on Pa-231(p, 2n)U-230 direct route with 12.8 MeV protons at 1 mA current for 24 h. After a 28 days waiting period required for undesirable product (U-230) activity to decrease sufficiently, this activity decreases to 21.4 mCi and by considering the average dose per patient as 0.5 mCi, these activities are enough for 43 patients. Besides, Pa-231 is already the target material in this direct production route and Pa-231 obtained from undesirable product U-231 can be stored and processed for re-use as the target material. In this way, a significant amount of source material can be recovered.en_US
dc.language.isoengen_US
dc.publisherPleiades Publishing Incen_US
dc.rightsinfo:eu-repo/semantics/closedAccessen_US
dc.subjectU-230en_US
dc.subjectAlpha Therapyen_US
dc.subjectDensity Modelsen_US
dc.subjectProduction Routesen_US
dc.titleAn investigation on production routes of U-230 radioisotope used in targeted alpha therapy by different level density modelsen_US
dc.typearticleen_US
dc.relation.ispartofMoscow University Physics Bulletinen_US
dc.departmentİstanbul Medipol Üniversitesi, Tıp Fakültesi, Dahili Tıp Bilimleri Bölümü, Nükleer Tıp Ana Bilim Dalıen_US
dc.identifier.volume77en_US
dc.identifier.issue6en_US
dc.identifier.startpage878en_US
dc.identifier.endpage885en_US
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanıen_US
dc.identifier.doi10.3103/S0027134922060170en_US
dc.institutionauthorCinoğlu Karaca, Merve
dc.identifier.wosqualityQ4en_US
dc.identifier.wos000935207100011en_US


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