Nuclear model analysis and optimization of production data of the medically interesting 66,67,68 Ga via alpha induced reactions on 63,65 Cu targets.

Evaluation of the 63Cu(α,n)66Ga, 65Cu(α,2n) 67Ga and 65Cu(α,n)68Ga reactions was done to study the production of medical radionuclides 66Ga, 67Ga and 68Ga respectively. 63Cu(α,2n)65Ga and 65Cu(α,3n)66Ga reactions were also evaluated for the estimation of radioisotopic impurities. Cross section data of each reaction were compiled and normalized to the standard values of decay data and monitor reaction. To check the consistency of the literature data, three nuclear model calculations were performed, using nuclear model codes; TAYLS 1.9, ALICE-IPPE, and EMPIRE 3.2. A well-developed evaluation methodology based on the normalized experimental data and nuclear model calculations was used to generate the statistically fitted cross sections. From the fitted cross sections, thick target yields for each reaction were calculated for the estimation of radioisotopic impurities. Finally, a suitable energy region for the production of 66Ga, 67Ga and 68Ga was suggested with a minimum level of radioisotopic impurities.

Evaluation of nuclear reaction cross sections for optimization of production of the important non-standard positron emitting radionuclide 89Zr using proton and deuteron induced reactions on 89Y target.

89Zr (T1/2 = 3.27 d) is an important ß+-emitting radionuclide of zirconium used in immuno PET. The excitation functions of the 89Y(d,2n)89Zr and 89Y(p,n)89Zr reactions were analyzed to deduce the optimum conditions for the high purity production of 89Zr. The nuclear model codes ALICE-IPPE, EMPIRE 3.2 and TALYS 1.9 were used to check the consistency and reliability of the experimental data. A polynomial fit to the chosen data for each reaction gave the excitation function, which was then used for the integral yield calculation of the product. The amount of the major radioactive impurity 88Zr was precisely analyzed for both the proton and the deuteron induced reactions on the 89Y target.

Evaluation of nuclear reaction cross sections for optimization of production of the emerging diagnostic radionuclide 55Co.

The excitation functions of the (54)Fe(d,n)(55)Co, (56)Fe(p,2n)(55)Co and (58)Ni(p,α)(55)Co reactions were analyzed with relevance to the production of the ß(+)-emitter (55)Co (T½=17.53 h), a promising cobalt radionuclide for PET imaging. The nuclear model codes ALICE-IPPE, EMPIRE and TALYS were used to check the consistency of the experimental data. The statistically fitted excitation function was employed to calculate the integral yield of the product. The amounts of the radioactive impurities (56)Co and (57)Co were assessed. A comparison of the three investigated production routes is given.

Evaluation of excitation functions of the (68,67,66)Zn(p,xn)(68,67,66)Ga and 67Zn(p,α)64Cu reactions: validation of evaluated data through comparison with experimental excitation functions of the (nat)Zn(p,x)(66,67)Ga and (nat)Zn(p,x)64Cu processes.

Experimentally available cross section data for formation of the radionuclides (68)Ga, (67)Ga, (66)Ga and (64)Cu in proton induced reactions on enriched (68)Zn, (67)Zn and (66)Zn were evaluated by comparison with the excitation functions calculated by the nuclear model codes, EMPIRE and TALYS, followed by statistical fitting of the selected data. The recommended cross sections were used to obtain the integral yields. The validation of the recommended excitation functions was also attempted by normalization to (nat)Zn and comparison with the experimental data for the (nat)Zn(p,x)(67)Ga, (nat)Zn(p,x)(66)Ga and (nat)Zn(p,x)(64)Cu processes.

Nuclear model analysis of excitation functions of proton induced reactions on 86Sr, 88Sr and natZr: Evaluation of production routes of 86Y.

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.

Activation cross-sections of proton induced reactions on natural Ni up to 65MeV.

Production cross-sections of the (nat)Ni(p,x)(60,61)Cu, (56,57)Ni, (55,56,57,58)Co nuclear reactions were measured in five experiments up to 65MeV by using a stacked foil activation technique. The results were compared with the available literature values, predictions of the nuclear reaction model codes ALICE-IPPE, TALYS-1.4, and extracted data from the TENDL-2012 library. Spline fits were made on the basis of selected data, from which physical yields were calculated and compared with the literature values. The applicability of the (nat)Ni(p,x)(57)Ni, (57)Co reactions for thin layer activation (TLA) was investigated. The production rate for (55)Co was compared for proton and deuteron induced reactions on Ni.

Activation cross-sections of deuteron induced reaction of natural Ni up to 40 MeV.

Production cross-sections of (nat)Ni(d,x)(56,57)Ni, (55,56,57,58)Co, (52,54)Mn, and (51)Cr nuclear reactions were measured up to 40 MeV by using the stacked foil technique. The results were compared with the literature values, TALYS 1.4 and TENDL-2012. Spline fits were made on the selected data, from which physical yields were calculated and compared with the literature and our directly measured thick target yield values. (nat)Ni(d,x)(56,57,58)Co reactions were analyzed for beam monitoring and thin layer activation (TLA). Rate of production of (55)Co was compared between proton and deuteron induced reactions.