Activation cross sections of alpha-particle-induced reactions on natural rhenium up to 50 MeV.

Activation cross sections of alpha-particle-induced reactions on natural rhenium were measured. The stacked-foil activation technique and high-resolution gamma-ray spectrometry were used to derive the cross sections. The production cross sections of 190g, 189g, 188g, 187g, 186g, 185, 184Ir, 185Os, and 184g, 183gRe were determined up to 50 MeV. The cross sections of 185,184Ir were measured for the first time. The experimental results were compared with previous experimental data and theoretical calculations in the TENDL-2021 library.

Alpha-particle-induced reactions on natural silver in the 10-50 MeV energy range: Production of 111In, 110mIn and 109Cd.

Production cross sections of medical radionuclides 111In, 110mIn and 109Cd were investigated in the α-particle-induced reactions on natural silver up to 50 MeV. The stacked-foil activation technique and γ-ray spectrometry were used to determine the cross sections. The excitation functions of byproducts 104g,105,106m,110mAg, 107,111mCd and 107g,108g,108m,109,110gIn were also determined. Physical yields of 111In, 110mIn and 109Cd were deduced based on the measured cross sections.

Determination of excitation function for alpha induced reactions on 237Np and 238Pu.

The excitation function of the alpha particle-induced reactions on 237Np and 238Pu has been determined for the incident alpha energies ranging from threshold to 50 MeV using TALYS1.95 nuclear reaction code. In this study, the excitation function of (α,xn) reactions on 237Np and 238Pu has been determined by invoking the Jeukenne-Lejeune-Mahaux-Bruyeres Optical model potential. The microscopic nuclear level density from Hilaire's combinatorial table is used to calculate the nuclear level density. Also, the excitation function has been evaluated by using the alpha potential of Watanabe folding approach with Koning-Delaroche spherical optical model potential and McFadden-Satchler potential. Furthermore, all the calculated cross-sections have been compared with the experimental results taken from EXFOR and the available evaluated cross-sections from TENDL2019 nuclear data library. The calculated cross sections using Jeukenne-Lejeune-Mahaux-Bruyeres Optical model potential together with microscopic nuclear level density from Hilaire's combinatorial table incorporating the Skyrme-Hartree-Fock-Bogoliubov calculation results in good correspondence with the experimental values from EXFOR.

Activation cross sections of proton-induced reactions on natural platinum up to 30 MeV.

Activation cross sections of proton-induced reactions on natural platinum were measured. The stacked-foil activation technique and high-resolution gamma-ray spectrometry were used. The production cross sections of 198, 196, 196m2, 195, 194, 193, 192, 191Au, 191Pt, and 192, 190Ir were determined up to 30 MeV. The experimental results were compared with previous experimental data and theoretical calculations in the TENDL-2019 library.

Excitation function of 54Fe(p,α)51Mn from 9.5 MeV to 18 MeV.

Excitation function of the 54Fe(p,α)51Mn reaction was measured from 9.5 to 18 MeV E 0 , p + by activating a foil stack of 54Fe electrodeposited on copper substrates. Residual radionuclides were quantified by HPGe gamma ray spectrometry. Both 51Mn (t 1/2 = 46.2 min, 〈 E ß + 〉 = 963.7 keV , I ß + = 97 % ; E γ = 749.1 keV, I γ = 0.265%) and its radioactive daughter, 51Cr (t 1/2 = 27.704d, E γ = 320.1 keV, I γ = 9.91%), were used to indirectly quantify formation of 51Mn. Results agree within uncertainty to the only other measurement in literature and predictions of default TALYS theoretical code. Final relative uncertainties are within ±12%.

Nuclear model prediction of cross-section for 125 - 119I radionuclides produced in proton + 125Te reaction at ≈ 5-100 MeV.

The theoretical model codes ALICE/ASH and TALYS-1.95(G) were used to make theoretical predictions of the production cross-sections of 125I, 124I, 123I, 122I, 121I, 120I, and 119I radionuclides produced in the interaction of proton-projectile with 125Te-target at energies ≈ 5-100 MeV. The results were compared with the measured values in the literature and with TENDL-2019 evaluated data. The Pearson's correlation coefficient indicates a strong and positive correlation between the predicted and the previously measured production cross-sections for medically important 125I, 124I, 123I, and 122I radionuclides. Further, the results show that the TALYS-1.95(G) code predicts more successful outcomes than the ALICE/ASH code for 125I, 124I, 123I, and 122I radionuclides production, which have widespread medical applications, particularly for diagnostic and therapeutic purposes.

Production cross sections of 52Mn in alpha-particle-induced reactions on natural vanadium.

Activation cross sections of alpha-particle-induced reactions on natural vanadium were measured. The production cross sections of 54, 52gMn, 51Cr, 48V, and 47, 46gSc were determined up to 50 MeV. The stacked-foil activation technique and high-resolution gamma-ray spectrometry were used. The experimental results were compared with previous experimental data and theoretical calculations in the TENDL-2019 library. The physical yield of the medical radionuclide 52gMn was derived from the measured cross sections.

Evaluation of nuclear reaction cross sections for optimization of production of the non-standard positron emitting radionuclide 90Nb using proton induced reactions on Zr target.

Niobium-90 radionuclide is one of the promising candidates for the positron emission tomography (PET) technique. In this study, 90Nb excitation functions via 90Zr(p,n) and natZr(p,xn) reactions were computed using the TALYS-1.95 code based on phenomenological and microscopic level density models. The MCNPX simulation code was used for each case. Moreover, the target thicknesses were obtained using the SRIM-2013 code and the theoretical and simulation-based production yields of the 90Nb were evaluated. The experimental production yield amounts of about 72.68 and 126.7 (both in MBq/µAh) for 90Zr(p,n) and natZr(p,xn) reactions in the corresponding optimal energy windows were attained by our experiments respectively.

Calculations for the nuclear reaction cross-sections via α-particle induced reactions on 65Cu to produce impurity free 67Ga for medical applications.

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.

Nuclear model prediction for production of medical 22Na, 51Cr, 60Co, 61Cu, 64Cu, 65Zn, 67, 68Ga, 88Y and 99Mo radionuclides: Comparison of experimental and theoretical data.

Theoretical nuclear model predictions were carried out to calculate the production cross sections of medically important 22Na, 51Cr, 60Co, 61Cu, 64Cu, 65Zn, 67, 68Ga, 88Y and 99Mo radionuclides produced in the interaction of α-projectile with 27Al, 51V, 59Co, 60Ni, 65Cu, 63Cu, 66Zn, 89Y and 96Zr targets respectively at energies ≈10-65 MeV. The production cross sections were predicted using ALICE/ASH and EMPIRE 3.2 nuclear model codes. The predicted results are discussed and compared with the experimental data in the literature.

Cross sections of 3He-particle induced reactions on 186W.

Irradiation of 186W targets by 3He particles was carried out. For the first time the cross sections for the reactions of production of 183, 184, 186, 188Re, 183, 185Os, 187W were measured by the stack foil technique in the 3He energy range of 15-45 MeV. The results were compared to the data from the TENDL-2019 library. Using the experimental excitation functions, the thick target yields of medically relevant rhenium radioisotopes were calculated.

Nuclear model analysis of the 65Cu(α, n)68Ga reaction for the production of 68Ga up to 40 MeV.

The charge particle (α) induced reactions on enriched copper (65Cu) are investigated for the production of 68Ga. The data sets of experimental cross sections are compiled, normalized and nuclear model analysis is done using calculational codes namely, ALICE-IPPE, TALYS 1.95 and EMPIRE 3.2. The theoretical production cross sections via alpha particle induced reactions are calculated to present a set of recommended cross sections. The calculated cross sections are utilized to deduce thick target yield (TTY) for the 65Cu (α, n) 68Ga reaction. The range of energy for production of 68Ga is suggested up to 40 MeV having least contribution of radio-impurities.

Production cross sections of 45Ti in the deuteron-induced reaction on 45Sc up to 24 MeV.

Activation cross sections of the medically interesting radionuclide 45Ti were investigated in the deuteron-induced reaction on 45Sc. 45Ti can be produced in a radioactive-contamination-free form in the 45Sc(d,2n)45Ti reaction below 15 MeV deuteron energy. The stacked foil activation technique and γ-ray spectrometry were used to determine the cross sections. The physical yield of 45Ti was deduced from the measured cross sections.

Cross sections of 56Fe(n, p)56Mn, 55Mn(n, p)55Cr, 52Cr(n, p)52V, 56Fe(n, α)53Cr, 55Mn(n, α)52V and 52Cr(n, α)49Ti reactions using phenomenological level density models from threshold to 20 MeV.

56Fe(n,p)56Mn, 55Mn(n,p)55Cr, 52Cr(n,p)52V, 56Fe(n, α)53Cr, 55Mn(n, α)52V and 52Cr(n, α)49Ti reactions are evaluated using four phenomenological nuclear level density models from reaction threshold to 20 MeV. The calculated data is compared with the experimental nuclear reaction data from EXFOR database. Statistical factors H, D and R are computed to identify the best fit. Level density parameters are adjusted for further improvement of the fitting. Back shifted Farmi-gas model gives a resemblance of neutron-induced 56Fe, 55Mn and constant temperature Fermi-gas model gives a closeness for 52Cr reaction with our new parameter values.

Cyclotron production of no carrier added 186gRe radionuclide for theranostic applications.

186gRe (T1/2 = 3.7183 d, E(ß-)mean = 346.7 keV, I(ß-)mean = 92.59%), a mixed beta and γ-emitter shows great potential for use in theranostic applications. The dominant 185Re(n,γ) route, via use of a nuclear reactor, provides 186gRe in carrier added form with low specific activity, while cyclotrons offer no carrier-added (NCA) high specific activity production of 186gRe. However, to be able to select the best possible nuclear reaction and to optimize the production route via the use of a cyclotron, information on the excitation function for the reaction of interest as well as for the competing reactions is necessary. Accordingly, we have conducted a detailed study of the excitation functions for natW(d, x) reactions in seeking optimized parameters for the NCA production of 186gRe. Noting a discrepancy among the experimental data, we made an evaluation of the available literature, finally selecting optimum parameters for the production of 186gRe via the 186W(d,2n)186Re reaction. These beam parameters were then used for batch production of 186gRe by irradiating an enriched 186W metallic powder target, followed by a subsequent automated chemical separation process. The preliminary results show 98.1% radionuclidic purity of 186gRe at 8 h subsequent to the End of Bombardment (EOB), offering the potential for use in clinical applications.

Cross section of the 96Zr(α,n)99Mo reaction induced by α-particles beams on natZr targets.

The excitation function of the 96Zr (α,n)99Mo reaction was determined using the stacked-foil activation technique. For the experiments, two stacks with metal foils of Cu, Ti and Zr of natural isotopic composition were irradiated independently with a 27.2 MeV α-particle beam. The characteristics of the primary beam and its verification along each stack were determined according to the well-known natCu(α,x)65Zn, natCu(α,x)66,67Ga, and natTi (α,x)51Cr monitor reactions. It was deduced that the expected production yield from 99Mo by irradiating 96Zr targets with a 23.8 MeV alpha particle beam for 1 h is 1.77 MBq/µA. According to the results, irradiation characteristics are proposed to produce 99Mo with high specific activity.

Nuclear model calculations on the production of auger electron emitter 111In: As a theranostic radionuclide.

The main goal of this study is the production investigation of the 111In as a diagnostic and mighty radionuclide in nuclear medicine especially in the Single Photon Emission Computed Tomography (SPECT) technique. Excitation functions based on four main phenomenological level density models were evaluated for the induced reactions; namely, 109Ag(α,2n), 110Cd(d,n),111Cd(p,n),112Cd(p,2n),natCd(p,xn) and natCd(d,xn) using the TALYS-1.8 and EMPIRE-3.2 nuclear codes. Furthermore, simulation code was used for the mentioned processes and, also, the 111In production yield predictions in each reaction were done. Finally, in order to certify the above calculation outcomes, a comparison with the existing data which were taken from EXFOR database was implemented.

Experimental investigation and theoretical evaluation of proton induced nuclear reactions on nickel.

The cross-sections for proton-induced nuclear reactions on natural nickel were experimentally measured for the natNi(p,x)60,61,64Cu, natNi(p,x)55,57,58Co and natNi(p,x)57Ni reactions from their respective thresholds up to 17 MeV proton energy. The stacked-foil technique in combination with HPGe γ-ray spectroscopy was used. Three codes were used in the theoretical calculations namely ALICE-IPPE, EMPIRE-3.2.2 and TENDL-2017. Comparison of the present results with the earlier reported experimental data and with the code results were carried out.

Production cross sections of 68Ga and radioactive by-products in deuteron-induced reactions on natural zinc.

Activation cross sections of the deuteron-induced reactions on natural zinc are studied for the production of the medical radionuclide 68Ga. The stacked foil activation method and the γ-ray spectrometry were used. Co-produced radionuclides 65,66,67Ga, 63,65,69mZn, 61Cu, and 58Co are also investigated to evaluate amounts of impurities for practical use of 68Ga. Physical yields of the radionuclides were deduced from the measured cross sections.

Production cross sections of ytterbium and thulium radioisotopes in alpha-induced nuclear reactions on natural erbium.

Activation cross sections of alpha-induced reactions on natural erbium were measured using a 50.9-MeV alpha-beam at the RIKEN AVF cyclotron. Well-established methods for the measurements, the stacked-foil activation technique and gamma-ray spectrometry, were used. Production cross sections of 166,169Yb and 165,166,167,168,170,173Tm were determined. This is the first measurement of the cross sections of 166,170Tm. The integral yield of the medical radionuclide 169Yb was derived from the measured excitation function.