Isomeric cross sections for the 90Zr(n, α)87Srm, 93Nb(n, α)90Ym and 92Mo(n, α)89Zrm reactions were measured at five neutron energies over the range 13.73 MeV-14.77 MeV using the activation technique in combination with high resolution γ-ray spectrometry. In the present work, the cross sections are measured for the 90Zr(n, α)87Srm and 93Nb(n, α)90Ym reactions are referenced to the 27Al(n, α)24Na standard reaction cross section whereas those measured for 92Mo(n, α)89Zrm reaction are referenced to the 56Fe(n, p)56Mn standard reaction cross section. The cross sections for these reactions were also theoretically estimated using the EMPIRE-3.2 and TALYS 1.8 codes over the neutrons energy range of 10 MeV-20 MeV and matched with the experimental cross sections by making a proper choice of the model parameters. A minimum eight different sets of these statistical model calculations were performed by using the consistent sets of model parameters along with the pre-equilibrium mechanism in addition to the direct-reaction and the statistical Hauser-Feshbach (HF) compound nucleus ones. The measured cross sections for these three reactions increase with the increase in neutron energy from 13.73 MeV to 14.77 MeV. As the proton number increased by one when we go from zirconium to niobium or from niobium to molybdenum, the probability of alpha particle emission also increases at each corresponding neutron energy. The present results indicate that the measured cross section at each neutron energy for the 92Mo(n, α)89Zrm reaction is found to be the highest as compared to the other two reactions whereas, for the 90Zr(n, α)87Srm reaction, the measured cross section is found to be the lowest as compared to the other two reactions studied. The results obtained from the present measurement are found to be in good agreement with the calculated reaction cross section based on theoretical models and also with the work reported by earlier authors.

Diagnostics field is facilitated with advancements enacted in anatomic imaging (cross-sectional modalities). Radionuclide scans (imaging) escorted by 67Ga are extensively beneficial in bone scintigraphy and recognition of prosthetic joint failure. Present work comprises the data concerning 67Ga production via α-particle induced nuclear reactions, TTY (thick target yield) and impurity analysis. Experimental measurements regarding 67Ga production are analyzed through a comparative study performed with calculations of theoretical model codes (TALYS-1.95, EMPIRE-3.2.3 and ALICE-IPPE). A data set of recommended cross-sections was generated and utilized to deduce TTY. The contribution of radionuclidic impurities is canvassed to suggest an energy region to produce impurity free 67Ga for medical applications.

The proton induced nuclear reactions on 55Mn were considered to investigate for the production of 52Fe. The experimental results obtained by 55Mn(p,4n)52Fe reaction were compared with the results of nuclear model calculations using the codes ALICE-IPPE, EMPIRE 3.2 and TALYS 1.9. The thick target yields (TTY) of 52Fe were calculated from the recommended excitation functions. Analysis of impurities was also discussed. A comparison of the various radio-impurities showed that for the production of 52Fe via 55Mn(p,4n)52Fe reaction, energy ranges from 70→45 MeV could be the method of choice, which gives high yield with minimum impurities to make it as a potential candidate for theranostic applications and in particular, Positron Emission Tomography (PET).

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.

Proton, deuteron and alpha-particle induced reactions on (87,88)Sr, (nat)Zr and (85)Rb targets were evaluated for the production of (87,88)Y. The literature data were compared with nuclear model calculations using the codes ALICE-IPPE, TALYS 1.6 and EMPIRE 3.2. The evaluated cross sections were generated; therefrom thick target yields of (87,88)Y were calculated. Analysis of radio-yttrium impurities and yield showed that the (87)Sr(p, n)(87)Y and (88)Sr(p, n)(88)Y reactions are the best routes for the production of (87)Y and (88)Y respectively. The calculated yield for the (87)Sr(p, n)(87)Y reaction is 104 MBq/μAh in the energy range of 14→2.7MeV. Similarly, the calculated yield for the (88)Sr(p, n)(88)Y reaction is 3.2 MBq/μAh in the energy range of 15→7MeV.

The proton induced nuclear reactions on (86)Sr, (88)Sr and (nat)Zr were investigated for the production of (86)Y. The literature data were compared with the results of nuclear model calculations using the codes ALICE-IPPE, TALYS 1.6 and EMPIRE 3.2. The thick target yields of (86)Y were calculated from the recommended excitation functions. Analysis of radioyttrium impurities was also performed. A comparison of the various production routes showed that for medical applications of (86)Y, the reaction (86)Sr(p,n)(86)Y is the method of choice, which gives efficient yield with minimum impurities.