Cross section empirical formulation for (n, 2n) nuclear reactions on natural isotopes from Z= 21 to Z= 79 for neutron energy range, 8-20 MeV.

Neutron induced reactions with different target materials and isotopes are very important for completion of nuclear data base as well as for many applications. Since the experimental determinations of the reaction cross sections for such reactions are not always available, attempts were made to introduce empirical or semi empirical formulae. In this work, new empirical formulation for (n, 2n) nuclear reactions on natural isotopes for neutron energies range 8-20 MeV, based on some published experimental works. The deuced formulae are then used to calculate the excitation functions for the (n,2n) on target isotopes having atomic numbers in the range 21-79. The cross section values for many reactions, having previously measured values, are determined and inter-comparison with the experimental and the TENDL-2019 database values are given using some statistical error parameters. Special attention was made to some Lanthanide isotopes. The results showed satisfied predictions in most cases.

New empirical formulae for (n, p) reaction cross sections on stable isotopes from Z= 21 to Z= 51 for energies up to 20 MeV.

Neutron Induced reactions on different target nuclei have get impact on many nuclear basic sciences and applications. Due to the lack of literature available experimental data for many targets, empirical formulae for the (n, p) reactions cross section on different targets and different incident neutron energies are formulated. The formulae are used for calculation of excitation functions for target isotopes having atomic numbers in the range from 21 to 51 and neutron energies from 20 MeV down to respective threshold energy of each reaction. The results are compared to the existing experimental results as well as the TENDL-2019 database values.

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.

Experimental yield and evaluation of proton induced reactions for neutron production and synthesis of beryllium-7 using lithium compounds as target material.

We had investigated the nuclear processes occur during nuclear reactions of protons with lithium containing targets. Experimental measurements were undertaken to obtain the thick-target yield of 7Be and infer upon the neutron production. Three candidate target materials having the chemical compositions LiF, LiBO2, and Li2B4O7 were used. The 7Be yield was probed using its 477 keV day γ-line while the neutron yield was probed using 63Cu(n,γ)64Cu. The 7Be and neutron yields were found different among the different compositions. Discussion on the details of Li (p,n) reactions and decay of exit channels are given and evaluated in order to explain the difference in yield among different target compositions and evaluate the nominal value of yield. Based on experimental results and evaluation, accumulation of 7Be in the target material limits its operation time for neutron production. The LiF targets gave the highest 7Be yield compared to water soluble LiBO2 and Li2B4O7. Neutron production may be undertaken with LiF target as well as lithium metaborate target with special attention to the target operation time.

Excitation functions and yield measurements for Proton Induced Reactions in Stainless Steel: Special relevance to Proton Activation Analysis.

In this work, the excitation functions for protons induced nuclear reactions with stainless steel's constituent elements were measured and the results were used in Proton Activation Analysis (PAA) of 18/10 steel samples which was carried out at Egyptian MGC-20 cyclotron. The elemental concentrations were also checked using the EDX technique. The reactions natFe(p,x)56Co, natNi(p,α)55Co and natCr(p,x)52gMn were studied from threshold up to 14.3 MeV proton energy. TALYS-1.6 and EMPIRE-3.2.2 codes were used to model the excitation functions of the investigated reactions. For quantitative analysis using PAA, the apparent reaction yields (i.e. not corrected for the γ-ray attenuation), were measured for each reaction along the proton energy range as well as the target thickness, and normalization factors were given.

Excitation function of proton induced nuclear reaction on strontium: Special relevance to the production of 88Y.

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.

New activation cross section data on longer lived radio-nuclei produced in proton induced nuclear reaction on zirconium.

The excitation functions of (96)Nb, (95m)Nb, (95g)Nb, (92m)Nb, (91m)Nb, (90)Nb, (95)Zr, (89)Zr, (88)Zr, (86)Zr, (88)Y, (87m)Y, (87g)Y, (86)Y were measured up to 70MeV proton energy by using the stacked foil technique and the activation method. The new data were compared with the critically analyzed experimental data in the literature and with the TALYS based model results in TENDL-2013 library. The possible role of the investigated reactions in the production of medically relevant (90)Nb, (95m)Nb, (89)Zr, and (88)Y radionuclides is discussed.

Excitation function of (3)He-particle induced nuclear reactions on natural palladium.

Excitation functions of (3)He-particle induced nuclear reactions on natural palladium were measured using the standard stacked foil technique and high resolution γ-ray spectroscopy. From their threshold energies up to 27MeV, cross-sections for (nat)Pd((3)He,x)(103,104,105,106m,110m,111,112)Ag and (nat)Pd((3)He,x)(104,105,107,111m)Cd reactions were measured. The nuclear model codes TALYS-1.4, and EMPIRE-3.1 were used to describe the formation of these products. The present data were compared to theoretical results and to the available experimental data. Integral yields for some important radioisotopes were determined.

Evaluation of different production routes for the radio medical isotope ²°³Pb using TALYS 1.4 and EMPIRE 3.1 code calculations.

(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.

Excitation function of ³He induced nuclear reactions on (nat)Pt up to 26 MeV.

The energy dependence of the cross-sections of (3)He-particle induced reactions on (nat)Pt targets was studied in the energy range from threshold up to 26 MeV, using a stacked-foil irradiation technique and classical gamma-spectroscopy. The formation of the radioisotopes via (nat)Pt((3)He,xn)(192)Hg, (nat)Pt((3)He,xn)(193 m,g)Hg, (nat)Pt((3)He,xn)(195m,g)Hg, (nat)Pt((3)He,xn)(197 m,g)Hg, (nat)Pt((3)He,xn)(199 m)Hg, (nat)Pt((3)He,pxn)(192,193,194,195,199,200 m)Au, (nat)Pt((3)He,pxn)(196 m,g)Au, (nat)Pt((3)He,pxn)(198 m,g)Au and (nat)Pt((3)He,2pxn)(197 m,199)Pt reactions were assessed. The obtained excitation functions were compared with the earlier published data and the theoretical model calculations by the codes ALICE-IPPE, EMPIRE-03, TALYS-1.4 and TENDL-2011 activation data library.

Cross-section measurements and nuclear model calculation for proton induced nuclear reaction on zirconium.

Proton induced nuclear reactions were measured with stacked-foil technique on natural zirconium targets up to 16.7MeV. Excitation functions were measured for the production of (90,92m,95m,95g,96)Nb and (88)Y. Cumulative cross-section, thick target yields and activation functions were deduced and compared with the available experimental data, as well as with the nuclear models codes; ALICE-IPPE, EMPIRE and TALYS. The integral yields for thick targets were deduced from the measured excitation function of the produced radionuclides.

Experimental studies and nuclear model calculations on proton induced reactions on manganese up to 45 MeV with reference to production of (55)Fe, (54)Mn and (51)Cr.

Excitation functions of the reactions (55)Mn(p,n)(55)Fe, (55)Mn(p,x)(54)Mn and (55)Mn(p,x)(51)Cr were measured from their respective thresholds up to 18 MeV in the first case and up to 45 MeV in the latter two cases, using the conventional stacked-foil technique. The radioactivity of (55)Fe was determined via high resolution X-ray spectrometry and of other radionuclides via high resolution γ-ray spectrometry. Nuclear model calculations were performed using the codes ALICE-IPPE, EMPIRE and TALYS. In some cases, good agreement was found between the experimental and theoretical data while in others considerable deviations were observed. From the experimental data the expected integral yields of the three investigated radionuclides were calculated.

Excitation functions of proton-induced reactions on natFe and enriched 57Fe with particular reference to the production of 57Co.

Excitation functions of the reactions (nat)Fe(p,xn)(55,56,57,58)Co, (nat)Fe(p,x)(51)Cr, (nat)Fe(p,x)(54)Mn, (57)Fe(p,n)(57)Co and (57)Fe(p,alpha)(54)Mn were measured from their respective thresholds up to 18.5MeV, with particular emphasis on data for the production of the radionuclide (57)Co (T(1/2)=271.8d). The conventional stacked-foil technique was used, and the samples for irradiation were prepared by an electroplating or sedimentation process. The measured excitation curves were compared with the data available in the literature as well as with results of nuclear model calculations. From the experimental data, the theoretical yields of the investigated radionuclides were calculated as a function of the proton energy. Over the energy range E(p)=15-->5MeV the calculated yield of (57)Co from the (57)Fe(p,n)(57)Co process amounts to 1.2MBq/microAh and from the (nat)Fe(p,xn)(57)Co reaction to 0.025MBq/microAh. The radionuclidic impurity levels are discussed. Use of highly enriched (57)Fe as target material would lead to formation of high-purity (57)Co.

Nuclear data for production of the therapeutic radionuclides 32P, 64Cu, 67Cu, 89Sr, 90Y and 153Sm via the (n,p) reaction: evaluation of excitation function and its validation via integral cross-section measurement using a 14 MeV d(Be) neutron source.

Nuclear data for production of the therapeutic radionuclides 32P, 64Cu, 67Cu, 89Sr, 90Y and 153Sm via (n,p) reactions on the target nuclei 32S, 64Zn, 67Zn, 89Y, (90)Zr and 153Eu, respectively, are discussed. The available information on each excitation function was analysed. From the recommended data set for each reaction the average integrated cross section for a standard 14 MeV d(Be) neutron field was deduced. The spectrum-averaged cross section was also measured experimentally. A comparison of the integrated value with the integral measurement served to validate the excitation function within about 15%. A fast neutron source appears to be much more effective than a fission reactor for production of the above-mentioned radionuclides in a no-carrier-added form via the (n,p) process. In particular, the possibility of production of high specific activity 153Sm is discussed.