Internal Dosimetry for Individuals Following Inhalation of Radionuclides | Research Square window.SnipcartSettings = { analytics: { enabled: false } }; (function() { var accessVector = localStorage.getItem('access_vector') || ''; window.dataLayer = window.dataLayer || []; if (accessVector) { window.dataLayer.push({ user: { profile: { profileInfo: { snid: accessVector } } } }); } })(); (function(w,d,s,l,i){w[l]=w[l]||[];w[l].push({'gtm.start':new Date().getTime(),event:'gtm.js'});var f=d.getElementsByTagName(s)[0],j=d.createElement(s),dl=l!='dataLayer'?'&l='+l:'';j.async=true;j.src='https://www.googletagmanager.com/gtm.js?id='+i+dl;f.parentNode.insertBefore(j,f);})(window,document,'script','dataLayer','GTM-K279D39R'); Browse Preprints In Review Journals COVID-19 Preprints AJE Video Bytes Research Tools Research Promotion AJE Professional Editing AJE Rubriq About Preprint Platform In Review Editorial Policies Our Team Advisory Board Help Center Sign In Submit a Preprint Cite Share Download PDF Method Article Internal Dosimetry for Individuals Following Inhalation of Radionuclides Taha M Taha, Tarek M Morsi This is a preprint; it has not been peer reviewed by a journal. https://doi.org/ 10.21203/rs.3.rs-3916083/v1 This work is licensed under a CC BY 4.0 License Status: Posted Version 1 posted You are reading this latest preprint version Abstract Background: Owing to the increasing use of radioisotopes whether in nuclear medicine or research. The current research paper uses a whole-body counter to assess internal contamination for individuals working in nuclear medicine and research laboratories. High purity germanium detector Whole Body Counter with a relative efficiency of 25%; aluminum endcap with 1.5 mm was calibrated using a mixed gamma source. It consists of three parts; high purity germanium detector gamma ray spectrometer, shielding room, and Phantom. Gamma internal monitoring was performed on eight volunteers inhaled with 131 I and two individuals contaminated with 99m Tc in organ geometry. Results: The committed effective dose for individuals was lower than dose constrain and within the dose limit according to ICRP recommendations. Conclusions: The study indicates that the HpGe whole body counter has the capability to detect organ contamination such as 131 I in thyroid gland, 99m Tc in whole body geometry. Nuclear Physics Whole Body Counter annual effective dose 131I 99mTc (HpGe) detector AccuScan II Full Text Additional Declarations The authors declare no competing interests. The study was approved by publication committee of Egyptian Atomic Energy Authority Cite Share Download PDF Status: Posted Version 1 posted You are reading this latest preprint version Research Square lets you share your work early, gain feedback from the community, and start making changes to your manuscript prior to peer review in a journal. As a division of Research Square Company, we’re committed to making research communication faster, fairer, and more useful. We do this by developing innovative software and high quality services for the global research community. Our growing team is made up of researchers and industry professionals working together to solve the most critical problems facing scientific publishing. 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