Excitation functions of natPb(d,x) 206,205,204,203,202Bi, 203cum,202m,201cumPb and 202cum,201cumTl reactions up to 50 MeV

Revisiting cross sections for proton induced reactions on natural lead between 10 and 80 MeV

This work is focused on the natPb(p,xn)207Bi reaction to extend earlier works on proton induced reactions for the determination of cross sections of residual nuclides. 207Bi decay (half-life 31.55 years) was measured by γ-ray spectrometry in 42 lead foils which had been irradiated by high proton fluxes 20 years ago. Since then, all short-lived radionuclides produced during the irradiation have decayed, so the background is strongly reduced and the cross section could be measured more precisely than during the original measurements. The results are found to be in very good agreement with the historical record. Additionally, theoretical calculations with modern Monte Carlo based codes were performed to compare the calculations of various Bi, Tl and Pb reactions with the historical data and with additional data from literature. The deviations of the new data from both theoretical calculations using EMPIRE and TALYS are discussed.

Overview and evaluation of different nuclear level density models for the 123I radionuclide production

The ¹²³I radionuclide (T_1/2 = 13.22 h, β+ = 100%) is one of the most potent gamma emitters for nuclear medicine. In this study, the cyclotron production of this radionuclide via different nuclear reactions namely, the ¹²¹Sb(α,2n), ¹²²Te(d,n), ¹²³Te(p,n), ¹²⁴Te(p,2n), ¹²⁴Xe(p,2n), ¹²⁷I(p,5n) and ¹²⁷I(d,6n) were investigated. The effect of the various phenomenological nuclear level density models such as Fermi gas model (FGM), Back-shifted Fermi gas model (BSFGM), Generalized superfluid model (GSM) and Enhanced generalized superfluid model (EGSM) moreover, the three microscopic level density models were evaluated for predicting of cross sections and production yield predictions. The SRIM code was used to obtain the target thickness. The ¹²³I excitation function of reactions were calculated by using of the TALYS-1.8, EMPIRE-3.2 nuclear codes and with data which taken from TENDL-2015 database, and finally the theoretical calculations were compared with reported experimental measurements in which taken from EXFOR database.