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  • 1 Agricultural, Medical and Industrial Research School, Nuclear Science and Technology Research Institute, P.O. Box 31485/498, Karaj, Tehran, Iran
  • | 2 Department of Medical Radiation Engineering, Science and Research Branch, Islamic Azad University, Tehran, Iran
  • | 3 Physics Faculty, University of Zanjan, Zanjan, Iran
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Radiolanthanide praseodymium-142 (T1/2 = 19.12 h, Eβ = 2.162 MeV (96.3%), Eγ = 1575 keV (3.7%)) due to its high β-emission and low specific γ-emission could not only be a therapeutic radionuclide, but also a suitable radionuclide in order for biodistribution studies. Conventionally, 142Pr produces via 141Pr(n,γ)142Pr reaction by irradiation in a low-fluence reactor and this study evaluates cyclotron reaction production of it. 142Pr excitation function via natLa(α,n)142Pr, 142Ce(p,n)142Pr, and natPr(d,p)142Pr reactions were calculated by TALYS-1.2 and EMPIRE-2.19beta codes, and with the data taken from the TENDL-2010 database. In addition, we compared them with the reported measurement by experimental data. Requisite thickness of targets was obtained by SRIM-2010 code for each reaction. The 142Pr production yield was evaluated with attention to excitation function and stopping power. Similar to reactor produced 142Pr; 141Pr impurity exists in cyclotron produced 142Pr while it could not be separated by chemical methods. Therefore, cyclotron and reactor produced 142Pr will be in carrier added form.

Manuscript Submission: HERE

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Journal of Radionalytical and Nuclear Chemistry
Language English
Size A4
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Founder Akadémiai Kiadó
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Publisher Akadémiai Kiadó
Springer Nature Switzerland AG
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ISSN 0236-5731 (Print)
ISSN 1588-2780 (Online)