Department of Nuclear Engineering
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Welcome to the Department of nuclear engineering, one of the leading academic and research centers in the field of nuclear engineering. With distinguished faculty members, advanced educational facilities, and a dynamic research environment, our faculty provides an excellent platform for the development of knowledge and specialized skills.
Our goal at the Department of nuclear engineering is to nurture competent, creative, and dedicated graduates who can play a significant role in scientific, industrial, and social fields. Our academic programs emphasize the latest scientific resources, applied research, and continuous interaction with the industry, preparing students for both professional careers and further academic pursuits.
Articles
Communications in Theoretical Physics (02536102)35(1)pp. 67-70
The excitation function for the fission of 230Th induced by neutrons has an unusual maximum for neutron energies in the vicinity of 700 KeV. It has been suggested that this maximum may be associated with the vibrational-mode resonance states. The unusual peak in the excitation function is interpreted in terms of a vibrational-mode resonance state in a two-humpted fission barrier. From theoretical fits to the fission cross sections and angular distributions, it is shown that the resonance has K = 1/2.
Physical Review C - Nuclear Physics (5562813)63(6)pp. 646071-646075
The statistical scission model is applied to fission fragment angular distributions from heavy-ion induced reactions. It is shown that the statistical scission model predicts angular distributions in good agreement with those measured from heavy-ion induced fission of some reaction systems where the fission barrier has vanished or is very small relative to the nuclear temperature. The statistical variances extracted from these model calculations are compared with their corresponding values from a microscopic theory, which includes nuclear pairing interaction. It is found that the values of statistical variance S20 are very sensitive to the pairing energy. The effects of pairing interaction on the fragment angular distributions are illustrated and discussed.
Journal of Nuclear Science and Technology (18811248)39pp. 828-830
Statistical scission model is applied to fission fragment angular distributions from heavy-ion induced Fission. Comparison of model calculations to experimental data on angular distributions for 11B, 12C and 14N on 209Bi system shows excellent agreement. It is shown that statistical scission model (SSM) predicts angular distributions in reasonable agreement with those measured for heavy-ion induced fission of some reaction systems where the fission barrier has vanished or is very small relative to the nuclear temperature. © 2014 Atomic Energy Society of Japan. All Rights Reserved.
Communications in Theoretical Physics (02536102)37(4)pp. 457-460
The level densities of even-odd and even-even isotopes 161,162Dy, 166Er and 171,172Yb were calculated using microscopic theory of interacting fermions and compared with experiments. It is found that the data can be well reproduced with level density formalism for nuclei with static deformation. The nuclear temperature as well as the entropy of nuclear system as a function of excitation energy has been extracted from the BCS theory. It is shown that the entropy exhibits an S-formed shape as a function of excitation energy. This is interpreted as a phase transition. Procedure of treating the even-odd and even-even nuclear systems has been presented and discussed.
Journal of Nuclear Science and Technology (18811248)39pp. 826-827
The level densities of 162Dy, 166Er and 172Yb are calculated using the microscopic theory of interacting fermions and is compared with experiment. It is concluded that the data can be reproduced with level density formalism for nuclei with static deformation. © 2014 Atomic Energy Society of Japan. All Rights Reserved.
Journal of Radioanalytical and Nuclear Chemistry (15882780)270(2)pp. 319-324
A reconnaissance study has been made on the distribution of 238U, 232Th, 40K, 137Cs and geochemical features in soil and sediment samples at various locations in the coast of Persian Gulf. Activity concentration levels due to radionuclides were measured in 50 samples of soils and sediments collected from the coast of Hormozgan. From the measured spectra, activity concentrations were determined for 40K (range from 140 to 1172 Bq·kg-1), 137Cs (from 0 to 15 Bq·kg-1), 238U (from 29 to 385 Bq·kg-1) and 2321Th (from 9 to 156 Bq·kg-1) with the lowest limit of detection (LLD) of 68, 3.2, 4.3 and 4.3 Bq·kg-1, respectively. The dose rate from ambient air at the soil ranges was between 23 to 177 nGy·h-1 with an average of 60±7.86 nGy·h-1. © 2006 Akadémiai Kiadó.
Iranian Journal of Science and Technology, Transaction A: Science (10286276)30(3)pp. 259-269
A reconnaissance study has been made on the distribution of 238U, 232Th, 40K, 137Cs and geochemical features in soil and sediment samples at various locations on the coast of Bushehr in the Persian Gulf. In this study a gamma-ray spectrometer based on a High Purity Germanium detector and a PC based MCA and X-ray fluorescence (XRF) method were used. Estimation of the measured radionuclide content have been made for the absorbed dose rate of gamma radiation. The Activity concentration (A), the equivalent radium (Req), and the external hazard index (Hex) which resulted from the natural radionuclides in soil and sediment are also calculated. The base-line data of radionuclides and heavy metals in view of the commissioning of nuclear and non-nuclear industries for the coast of Bushehr, which does not yet exist, was obtained. Activity concentration levels due to radionuclides were measured in 50 soil and sediment samples collected from this region. The measurement was performed with respect to their gamma radioactivity for a counting time of 24 hour intervals. From the accumulated spectra, activity concentration were determined for 40K (range from 108 to 520 Bq Kg-1), 137Cs (from 6 to 40 Bq Kg-1), 238U (from 12 to 75 Bq Kg1) and 232Th (from 8 to 33 Bq Kg-1) with the lowest limit detection (LLD) of, respectively, 68, 3.2, 4.3 and 4.3 Bq Kg-1. The dose rate from ambient air at the soil ranges was between 14 to 44 nGy h-1 with an average of 30.56 ± 7.86 nGy h -1. © Shiraz University.
Journal of Radioanalytical and Nuclear Chemistry (15882780)268(3)pp. 539-544
A nonlinear function was applied in combination with the method of mixing activity calibration for fitting the experimental peak efficiency of HPGe spectrometers in the 50-2614 keV energy range. The preparation of Marinelli beaker standards of mixed gamma- and RG-Set at secular equilibrium with its daughter radionucliedes was studied. Self-absorption was measured for the activity calculation of the gamma-ray lines for daughters of 238U series, 232Th series, as well as 137Cs and 40K in soil samples. Self-absorption in the sample depends on a number of factors including sample composition, density, sample size and gamma-ray energy. Seven Marinelli beaker standards were prepared in different degrees of compaction with bulk density (ρ) of 1.000 to 1.600 g·cm-3. The detection efficiency versus density was obtained and the equation of self-absorption correction factors was calculated for soil samples. © 2006 Akadémiai Kiadó.
Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms (0168583X)263(2)pp. 473-476
In this work thermal neutron self-shielding in aqueous bulk samples containing neutron absorbing materials is studied using bulk sample prompt gamma neutron activation analysis (BSPGNAA) with the MCNP code. The code was used to perform three dimensional simulations of a neutron source, neutron detector and sample of various material compositions. The MCNP model was validated against experimental measurements of the neutron flux performed using a BF3 detector. Simulations were performed to predict thermal neutron self-shielding in aqueous bulk samples containing neutron absorbing solutes. In practice, the MCNP calculations are combined with experimental measurements of the relative thermal neutron flux over the sample's surface, with respect to a reference water sample, to derive the thermal neutron self-shielding within the sample. The proposed methodology can be used for the determination of the elemental concentration of unknown aqueous samples by BSPGNAA where knowledge of the average thermal neutron flux within the sample volume is required. © 2007 Elsevier B.V. All rights reserved.
Annals of Nuclear Energy (03064549)35(12)pp. 2313-2320
This paper describes the application of a multilayer cellular neural network (CNN) to model and solve the time dependent one-speed neutron transport equation in slab geometry. We use a neutron angular flux in terms of the Chebyshev polynomials (TN) of the first kind and then we attempt to implement the equations in an equivalent electrical circuit. We apply this equivalent circuit to analyze the TN moments equation in a uniform finite slab using Marshak type vacuum boundary condition. The validity of the CNN results is evaluated with numerical solution of the steady state TN moments equations by MATLAB. Steady state, as well as transient simulations, shows a very good comparison between the two methods. We used our CNN model to simulate space-time response of total flux and its moments for various c (where c is the mean number of secondary neutrons per collision). The complete algorithm could be implemented using very large-scale integrated circuit (VLSI) circuitry. The efficiency of the calculation method makes it useful for neutron transport calculations. © 2008 Elsevier Ltd. All rights reserved.
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