Cross-sections of (n,p) reaction at a neutron energy of 14–15 MeV (original) (raw)
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Phenomenological approach affecting of (n, p) reaction cross sections via 14.5-MeV neutrons
Indian Journal of Physics, 2018
A new systematic formula is suggested to evaluate the (n, p) reaction cross sections at neutron energy of 14.5 MeV based upon the reaction's Q-value dependence, explicit symmetry breaking, and shell effects. The measured data for the (n, p) reaction cross sections have been gathered from the available literature, and then, it was analyzed for isotopes having 3 B Z B 83. It has been noted that the plot of r (n,p) against Z A 3=2 À Á , N À Z þ 1 ð Þ A 4=3 À Á and N=Z Á A 2=3 À Á is more efficient in determining the (n, p) reaction cross sections, as the reaction Q-value is related to values of r (n,p) too, which has been adequately represented and compared to other terms such as S p , S n , and S a separation energies. The odd-even effects investigated in the cross sections of odd-mass nuclei are higher than those of their neighboring eveneven nuclei close to magic numbers. The estimates of the current formula are compared with the experimental data gathered from the literature, and they are found to be in good agreement.
The Systematics Study of (n, p) Reaction Cross-Sections at 14.7 MeV Neutron Energy
World Journal of Nuclear Science and Technology, 2022
Based on the statistical model and taking into account the Q-value dependence and odd-even effects, we proposed a new empirical formula to reproduce the cross sections of the (n, p) reactions at 14.7 MeV neutron energy and at the target mass number 14 ≤ A ≤ 198 for even A and 29 ≤ A ≤ 205 for odd A. All calculated results from the proposed empirical formula were compared to the experimental data as well as the available semi-empirical formula obtained by other authors. A high level of agreement has been found between the collected experimental data and the most of semiempirical formulae obtained by others.
Journal of Radioanalytical and Nuclear Chemistry, 1998
The (n,2n) threshold reaction cross-sections, available in the literature are analysed for nuclei with 20≤Z≤92 in the neutron energy range of about 14.5 MeV. An empirical formula based on multiple regression technique is proposed for quick estimation of the (n,2n) reaction cross sections. The results obtained are compared with experimental data and those from other empirical formulae as long as byN-Z systematic. The validity of this formula is discussed.
An empirical fit to estimated neutron emission cross sections from proton induced reactions
Pramana, 2003
Neutron emission cross section for various elements from 9 Be to 209 Bi have been calculated using the hybrid model code ALICE-91 for proton induced reactions in the energy range 25 MeV to 105 MeV. An empirical expression relating neutron emission cross section to target mass number and incident proton energy has been obtained. The simple expression reduces the computation time significantly. The trend in the variation of neutron emission cross sections with respect to the target mass number and incident proton energy has been discussed within the framework of the model used.
(n,2n) and (n,3n) Neutron Induced Reaction Cross Sections above 8 MeV
Acta Physica Polonica A, 2015
Neutron induced reaction cross sections for (n,2n) and (n,3n) have been calculated in the energy range between 8 MeV and 26 MeV. Calculations were made for the target nuclei; 45 Sc, 59 Co, 89 Y, 93 Nb, 103 Rh, 169 Tm, 175 Lu, 181 Ta, 197 Au, 209 Bi. Calculated results were compared with the available data in EXFOR. Model calculations of present data indicated clearly that some reported data from measurements failed to separate (n,2n) and (n,3n) contributions.
Systematic study of (n,p) reaction cross sections from the reaction threshold to 20 MeV
Physical Review C, 2012
The cross sections of nat Cr(n,x) 52 V, 52 Cr(n,p) 52 V, nat Cr(n,x) 53 V, 53 Cr(n,p) 53 V, nat Zn(n,x) 66 Cu, 66 Zn(n,p) 66 Cu, nat Zn(n,x) 68 Cu m , 68 Zn(n,p) 68 Cu m , nat Mo(n,x) 97 Nb g , 97 Mo(n,p) 97 Nb g , nat Mo(n,x) 97 Nb m , 97 Mo(n,p) 97 Nb m , nat Sn(n,x) 116 In m1+m2 , 116 Sn(n,p) 116 In m1+m2 , nat Sn(n,x) 117 In g , 117 Sn(n,p) 117 In g , nat Sn(n,x) 118 In m1+m2 , 118 Sn(n,p) 118 In m1+m2 , nat Sn(n,x) 120 In x , 120 Sn(n,p) 120 In x , nat Ba(n,x) 138 Cs, and 138 Ba(n,p) 138 Cs reactions have been measured at 14.8 MeV neutron energy. In the present work, the contributions of (n,np), (n,pn), and (n,d) reactions from heavier isotopes are subtracted. The cross sections were also estimated with the TALYS-1.2 nuclear model code using different level density models, at neutron energies varying from the reaction threshold to 20 MeV. The variations in the (n,p) cross sections with the neutron number in the isotopes of an element are also discussed in brief.
Annals of Nuclear Energy, 2004
Activation cross sections of (n, p) and (n, a) reactions were measured by means of the activation method in the neutron energy range of 3.5-5.9 MeV using a deuterium gas target. The irradiated target isotopes were 27 Al, 28,29 Si, 41 K, 51 V, 61 Ni, 65 Cu, 64,67 Zn, 69 Ga, 79 Br, 92 Mo and 93 Nb. The cross sections of the 29 Si(n, p) 29 Al, 67 Zn(n, p) 67 Cu, 69 Ga(n, p) 69m Zn, 79 Br(n, p) 79m Se, and 69 Ga(n, a) 66 Cu reactions were obtained for the first time in the studied energy range. The d-D neutrons were generated by the deuterium gas target at the Van de Graaff accelerator (KN-VdG) at Nagoya University. All cross section values were determined relative to those of the 115 In(n, n 0 ) 115m In reaction. The activities induced by the low-energy neutrons were corrected. For the corrections, the neutron spectra and mean neutron energies at the irradiation positions were calculated taking into account the energy loss of incident deuterons, the angular differential cross section of the d-D reaction and the solid angle subtended by the sample. The systematics of the (n, p) reactions at the neutron energy of 5.0 MeV in the mass range between 27 and 92 were proposed for the first time. This systematics can predict the cross sections within an accuracy of a factor of 1.6.
Applied Radiation and Isotopes, 2012
In this study, activation cross sections were measured for the reaction of 232 Th(n,2n)231Th (T 1/2 = 25.5 h) by using neutron activation technique at six different neutron energies from 13.57 and 14.83 MeV. Neutrons were produced via the 3 H(2 H,n)4He reaction using SAMES T-400 neutron generator. Irradiated and activated high purity Thorium foils were measured by a high-resolution c-ray spectrometer with a highpurity Germanium (HpGe) detector. In cross section measurements, the corrections were made for the effects of c-ray self-absorption in the foils, dead-time, coincidence summing, fluctuation of neutron flux, low energy neutrons. For this reaction, statistical model calculation, which the pre-equilibrium emission effects were taken into consideration, were also performed between 13.57 and 14.83 MeV energy range. The cross sections were compared with previous works in literature, with model calculation results, and with evaluation data bases
An extensive assessment of the predictive capabilities of different nuclear models in the reproduction of experimental activation and transmutation cross- sections for neutron induced reactions is presented. Experimental EXFOR data have been processed and treated in order to systematically analyze all the available measurements for target nuclei from 27Al to 209Bi with energy of the projectile above 0.1 MeV. Experimental data have been compared with the correspondent simulations performed by means of the TALYS code and the ALICE/ASH code using different models for the description of the nuclear level densities at equilibrium states, these being both phenomenological and microscopic ones. The comparison between measurements and calculations is quantified by means of different statistical deviation factors, which are given as functions of the target nuclei mass number and of different channels. Recommendations are provided to the users on the best combinations of codes and models to o...
Applied Radiation and Isotopes, 2008
The cross-sections of 180 W(n,2n) 179m W, 186 W(n,2n) 185m W, 165 Ho(n,2n) 164m Ho, 64 Ni(n,a) 61 Fe, 165 Ho(n,a) 162 Tb and 51 V(n,p) 51 Ti reactions induced by neutrons around 14 MeV were measured using activation technique and calculated by a previously developed formula in this work. The neutron flux was determined using the monitor reactions 93 Nb(n,2n) 92m Nb and 27 Al(n,a) 24 Na, the neutron energies were measured with the method of cross-section ratios for 90 Zr(n,2n) 89 Zr to 93 Nb(n,2n) 92m Nb reactions. The results of this work are compared with data published previously. r