47Sc could be used in SPECT imaging and also suitable for targeted therapy of small tumors. The excitation functions for the production of 47Sc and accompanying impurities via proton and deuteron bombardment of Calcium, Titanium and Vanadium targets were evaluated by three nuclear codes, ALICE, TALYS and EMPIRE. Therefrom, integral yields of 47Sc and also 46gSc as a main impurity were calculated. The various production routes of 47Sc were compared together. The results consistency with available experimental data was checked for each reaction. Based on the results, the 46Ca(d,n)47Sc reaction can leads to the high purity 47Sc with the moderate yield.

Excitation functions were measured by the activation method using stacked-foil technique for the natSr(p,xn)88,87m,g,86m,gY reactions up to 18 MeV. The experimental results were compared with the theoretical data from EMPIRE-3.2 code and TENDL. Integral yields of 88,87m,g,86m,gY were estimated based on the measured cross sections. The optimum energy range for the production of the important isotope 88Y is Ep = 16→11 MeV, 88Y yield amounts to about 3 MBq/µAh.

The 123I radionuclide (T1/2 = 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.

Excitation functions were calculated for the α-particle induced reactions 115In(α,x)117mSn, 114Cd(α,n)117mSn, 116Cd(α,3n)117mSn and natCd(α,x)117mSn to analyse the production of the medically important 117mSn (T½ = 13.6 d). For calculations three nuclear model codes (i.e. TALYS, EMPIRE and ALICE-IPPE) were used and the results were compared with the available experimental data. For the most important reaction, 116Cd(α,3n)117mSn, evaluated data are presented. The yield and radionuclidic purity of 117mSn from each reaction are discussed.

The radionuclide zirconium-89 can be employed for the positron emission tomography (PET). In this study 89Zr excitation function via 89Y(p,n)89Zr reaction was calculated by the TALYS-1.8 code based on microscopic level density model. The formation of 89Zr was simulated using the Monte Carlo simulation code MCNPX to calculate the integral yield in the 89Y target body for threshold up to 40MeV incident-proton energy. The target thickness was based on calculation of the stopping power using the SRIM-2013 code matched to any incident-proton energy. The production yield of the 89Zr simulated with the Monte Carlo method for the 89Y(p,n)89Zr, 89Y(d,2n)89Zr, natSr(α,xn)89Zr and natZr(p,pxn)89Zr reactions and the results were in good agreement with published experimental results for the optimum energy range. An experimental yield of 53.1MB/µA for the 15MeV proton-induced on Y2O3 powder as a disk-target obtained for 1h irradiation at the AMIRS cyclotron.

The radioisotope 87Y is one of the candidates for the SPECT and 87Y/87mSr generator due to its suitable half-life and decay properties. The proton-induced on the 89Y target can be used for the production of 87Y. The present perusal calculated the excitation function for the both 89Y(p,x)87m,gY direct reaction and decay of 87Zr via 89Y(p,3n)87Zr → 87mY → 87gY indirect reaction using the TALYS-1.8 code. To simulation the production of 87m,gY nuclide, the target thickness was designed based on the stopping power calculation by the SRIM-2013 code. The Monte Carlo code GEANT4 was used to simulate the transport of protons through the irradiation assembly. Then, the cumulative integral yield of the 87m,gY has been calculated directly after the decay of 87Zr radionuclide entirely. These results were in good agreement with the theoretical and reported experimental data. Eventually, the integral yield of the 87m,gY was calculated by the indirect method from 87Zr decay after separation the zirconium. This work provides the basis for theoretical appraisement of the use of no-carrier-added 87Y as radiopharmaceutical for the purpose of medical applications.

Cross sections of alpha particle induced nuclear reactions have been measured on thin natural cadmium targets foils in the energy range from 11 to 51.2MeV. This work was a part of our systematic study on excitation functions of light ion induced nuclear reactions on different target materials. Regarding the cross sections, the alpha induced reactions are not deeply enough investigated. Some of the produced isotopes are of medical interest, others have application in research and industry. The radioisotope 117mSn is a very important theranostic (therapeutic + diagnostic) radioisotope, so special care was taken to the results for that isotope. The well-established stacked foil technique followed by gamma-spectrometry with HPGe gamma spectrometers were used. The target and monitor foils in the stack were commercial high purity metal foils. From the irradiated targets 117mSn, 113Sn, 110Sn, 117m,gIn, 116mIn, 115mIn, 114mIn, 113mIn, 111In, 110m,gIn, 109mIn, 108m,gIn, 115gCd and 111mCd were identified and their excitation functions were derived. The results were compared with the data of the previous measurements from the literature and with the results of the theoretical nuclear reaction model code calculations TALYS 1.8 (TENDL-2015) and EMPIRE 3.2 (Malta). From the cross section curves thick target yields were calculated and compared with the available literature data.

Activation cross-sections data of longer-lived products of proton induced nuclear reactions on dysprosium were extended up to 65MeV by using stacked foil irradiation and gamma spectrometry experimental methods. Experimental cross-sections data for the formation of the radionuclides (159)Dy, (157)Dy, (155)Dy, (161)Tb, (160)Tb, (156)Tb, (155)Tb, (154m2)Tb, (154m1)Tb, (154g)Tb, (153)Tb, (152)Tb and (151)Tb are reported in the 36-65MeV energy range, and compared with an old dataset from 1964. The experimental data were also compared with the results of cross section calculations of the ALICE and EMPIRE nuclear model codes and of the TALYS nuclear reaction model code as listed in the latest on-line libraries TENDL 2013.

(203)Pb radio-medical isotope has found great field of applications in nuclear medicine over the last decades. The previously measured excitation functions for the production of this isotope from different reactions were discussed, in order to confirm the most reasonable ones. Fitting curves were given for some reactions leading to the production of this isotope. The theoretical models TALYS 1.4, and EMPIRE 3.1 were used to construct the excitation functions for protons, deuterons, helium-3 and helium-4 induced reactions on Tl and Hg targets. The results of different models were compared with each other as well as with the collected experimental results, using the mean weighted deviation (F), and the relative variance (D) statistical parameters. Thick target yields were estimated, based on the discussed excitation functions, and compared with some measured values.

The existing cross section data of the (nat)Eu(d,x) and (nat)Eu(p,x) reactions relevant for the production of (147,149)Gd were expanded up to 70.9 MeV and 44.8 MeV, respectively. Integral yields of radiogadolinium were calculated, showing production rates higher than for the earlier proposed irradiation of highly enriched (144)Sm with α- or (3)He-particles. The formation of radioisotopic impurities like (151)Gd (T(1/2)=124 d) and (153)Gd (T(1/2)=240 d) was below 5%. Production of (147,)(149)Gd using enriched europium is also discussed.