Articles
Mirzayev, M.N.,
Nasri nasrabadi, M.,
Tiep n.v., N.,
Samedov o.a., O.,
Moslemi-mehni, E.,
Samadov s.f., S. Vacuum (0042207X)238
This research investigates the microstructure and surface morphology of ZrC nanocrystals irradiated with gamma quanta at energy levels of 1.17 MeV and 1.33 MeV, with absorption doses of 1500 and 3000 kGy. A 60Co isotope served as the gamma radiation source, and experiments were conducted under normal atmospheric conditions at room temperature. Analysis techniques included Fourier-transform infrared spectroscopy (FTIR), scanning electron microscopy (SEM—ZEISS, ΣIGMA VP), and transmission electron microscopy (TEM—Talos F200i). Gamma radiation induced the formation of new functional groups, transformed chemical bonds, and created active oxide centers on ZrC crystal surfaces. SEM results indicated nanoparticle mobilization with increased radiation absorption doses, while TEM analyses revealed amorphous oxide layers and a particle size increase to 23.46 nm at 3000 kGy. © 2025 Elsevier Ltd
Physics of Particles and Nuclei Letters (15318567)22(2)pp. 255-259
Abstract: The photofission which is very important for various nuclear applications involves the excitation and subsequent fission of a nucleus by photon absorption. This study explores the complexities of 237Np photofission, highlighting the critical roles of nuclear level density at saddle points and fission barrier parameters. Using advanced theoretical models and nuclear reaction codes, the research investigates the interplay between these factors and the photofission cross sections of 237Np. Theoretical results are compared with experimental data to deepen our understanding of photofission dynamics. © Pleiades Publishing, Ltd. 2025.
Samadov s.f., S.,
Ismayilova n.a., ,
Tuyen l.a., ,
Nasri nasrabadi, M.,
Trung n.v.m., ,
Tiep n.v., N.,
Samedov o.a., O.,
Mustafayev i.i., ,
Jabarov s.h., ,
Donkov a.a., Journal of the European Ceramic Society (1873619X)45(13)
In this work, the evolution of defects in zirconium carbide (ZrC) nanocrystals under gamma irradiation was studied using both experimental and computational approaches. Positron Annihilation Spectroscopy (PAS) and Raman spectroscopy were used to characterize radiation-induced defects, structural changes, and vibrational modes in ZrC samples. Density Functional Theory (DFT) calculations revealed that the displacement damage in the ZrC lattice increased with irradiation dose, and the increase in defects led to a significant decrease in Young's modulus and to lower hardness. Irradiation at 3000 kGy enhances defect evolution by creating carbon vacancies that potentially combine with existing defects to form larger vacancy clusters. In the Raman spectra, a new peak due to Sp2 C-C was detected at 1795 cm−1 at an absorption dose of 3000 kGy. The intensity ratio of the ID/IG band decreased from 1.133 (initial) to 1.09 (3000 kGy), reflecting amorphization and the formation of an oxide layer. These findings provide a foundation for future investigations aimed at optimizing the radiation tolerance of ZrC-based materials for advanced nuclear applications. © 2025 Elsevier Ltd
Physics of Plasmas (1070664X)32(5)
Inertial electrostatic confinement (IEC) is a method utilized to confine particles in fusion reactions. In an IEC device, ions are accelerated toward the center by an electric field created through the application of a potential difference between the anode and the cathode. This issue increases in ion density at the center and enhances the probability of collisions, thereby facilitating fusion reactions. Neutron production rate and the confinement time (CT) are the key parameters in an IEC device. Previous studies simulated the effects of various parameters, such as pressure, the number of cathode rings, and the dielectric thickness of the feed-stalk, on CT, comparing the results with experimental data. Results indicated that at low pressures, CT decreased due to asymmetry in the electric field caused by the feed-stalk. This study simulated the effect of an ion gun on CT and proposed adding a second feed-stalk opposite the first to reduce field asymmetry and improve CT at lower pressures. Simulations conducted at a pressure of 1 × 10 − 7 Torr and a voltage of −250 kV resulted in a CT of 14 570 μs, notably higher than previous findings, underscoring the beneficial influence of the second feed-stalk on the CT. © 2025 Author(s).
Radiation Physics and Chemistry (18790895)229
In this work, the IECF device using the MCNPX code was simulated and parameters such as lethargy as well as cross-sections, changes in neutron flux and dosimetry and suitable multi-layer shields were studied. To secure the device from radiation hazards at different work intensities and in addition to the role of shielding, the role of producing materials such as lithium, the required simulations were done and the necessary shield thicknesses were determined. From the intensity of 106s−1 which is used for nuclear laboratories in universities up to neutron production 1012s−1 which is used for the BNCT method, an optimal shield thickness is required. For the first layer, a material with an average mass number was chosen to absorb the highest amount of energy and produce the lowest amount of gamma in inelastic scattering with fast neutrons. The produced gammas are also absorbed by concrete. For the thickness changes of different layers, in addition to measuring the remaining energies in the neutron flux, the cross-sections corresponding to those energies were also measured in order to calculate the required shield thicknesses for different powers of the device in different working conditions. After determining the type of different materials suitable for shielding, dosimetry was performed according to the ICRP60 standard and by making the necessary changes in the thickness of the layers, the neutron and gamma doses were reduced to the standard level. Also, the fluxes of thermal, epithermal and fast neutrons were measured in different shielding layers. Finally, for all calculated neutron production intensities, the necessary shielding thickness was determined for safe operation of the device. As a result of this study, by modifying and improving the method of determining the required thickness of the shield for different intensities, the smaller and more suitable thickness for the intensity of 109 s−1 was determined. This improvement and reduction in the thickness of the shield caused a reduction in the weight of the total shield and a reduction in the cost of shield construction while maintaining radiation safety according to ICRP60 standards. The idea of lithium production by IECF device using the materials of this shielding was simulated by MCNPX code. Boric acid was investigated and studied as a suitable material for lithium production. After performing the simulation and calculations, the amount of 1 Kg of lithium per month of device working for 8 h per day was obtained which is a valuable amount and it is possible to increase its production. © 2024
