Practicality of the cyclotron production of radiolanthanide ~(142)Pr: A potential for therapeutic applications and biodistribution studies

摘要

Radiolanthanide praseodymium-142 (T _(1/2) = 19.12 h, E _β~- = 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, ~(142)Pr produces via ~(141)Pr(n,γ)~(142)Pr reaction by irradiation in a low-fluence reactor and this study evaluates cyclotron reaction production of it. ~(142)Pr excitation function via natLa(α,n) ~(142)Pr, ~(142)Ce(p,n)~(142)Pr, and ~(nat)Pr(d,p)~(142)Pr 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 ~(142)Pr production yield was evaluated with attention to excitation function and stopping power. Similar to reactor produced ~(142)Pr; ~(141)Pr impurity exists in cyclotron produced ~(142)Pr while it could not be separated by chemical methods. Therefore, cyclotron and reactor produced ~(142)Pr will be in carrier added form.