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.

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.

Radiological impact of natural radioactivity in Egyptian phosphate rocks, phosphogypsum and phosphate fertilizers.

In this study, the activity concentrations of the natural radionuclides in phosphate rocks and its products were measured using a high- purity germanium detector (HPGe). The obtained activity results show remarkable wide variation in the radioactive contents for the different phosphate samples. The average activity concentration of 235U, 238U, 226Ra, 232Th and 40K was found as (45, 1031, 786, 85 and 765Bq/kg) for phosphate rocks, (28, 1234, 457, 123 and 819Bq/kg) for phosphate fertilizers, (47, 663, 550, 79 and 870Bq/kg) for phosphogypsum and (25, 543, 409, 54 and 897Bq/kg) for single super phosphate respectively. Based on the measured activities, the radiological parameters (activity concentration index, absorbed gamma dose rate in outdoor and indoor and the corresponding annual effective dose rates and total excess lifetime cancer risk) were estimated to assess the radiological hazards. The total excess lifetime cancer risk (ELCR) has been calculated and found to be high in all samples, which related to high radioactivity, representing radiological risk for the health of the population.

Determination of concentrations of Fe, Mg, and Zn in some ferrite samples using neutron activation analysis and X-ray fluorescence techniques.

Mg-Zn ferrite is considered as one of the important materials with potential uses in many applications. In this work, samples of ferrite Mg(1-x)ZnxFe2O4 (where x=0.0, 0.2, 0.4, 0.6, 0.8 and 1) were synthesized by the sol-gel method for use in some hyperthermia applications. The composition and purity of the prepared samples hardly affected their properties. Therefore, the elemental concentration of these samples was measured by the X-ray fluorescence technique and thermal neutron activation analysis to check the quality of the prepared samples. The results of both methods were compared with each other and with the molecular ratios of the as-prepared samples. In addition, no existing elemental impurity, with considerable concentration, was measured.

Evaluation of radiation hazard potential of TENORM waste from oil and natural gas production.

In this study, a potential radiation hazard from TENORM sludge wastes generated during exploration and extraction processes of oil and gas was evaluated. The activity concentration of natural radionuclides (238)U, (226)Ra and (232)Th were determined in TENORM sludge waste. It was found that sludge waste from oil and gas industry is one of the major sources of (226)Ra in the environment. Therefore, some preliminary chemical treatment of sludge waste using Triton X-100 was also investigated to reduce the radioactivity content as well as the risk of radiation hazard from TENORM wastes. The activity concentrations of (226)Ra and (228)Ra in petroleum sludge materials before and after chemical treatment were measured using gamma-ray spectrometry. The average values of the activity concentrations of (226)Ra and (228)Ra measured in the original samples were found as 8908 Bq kg(-1) and 933 Bq kg(-1), respectively. After chemical treatment of TENORM samples, the average values of the activity concentrations of (226)Ra and (228)Ra measured in the samples were found as 7835 Bq kg(-1) and 574 Bq kg(-1), respectively. Activity concentration index, internal index, absorbed gamma dose rate and the corresponding effective dose rate were estimated for untreated and treated samples.