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.