h. khalafi

One of the most essential success factors of military and security organizations, especially in crises, is command. Martyer Soleimani was one of the successful national and resistance axis commanders who, with her command style, where able to bring great victories to the resistance axis and the Islamic Republic of Iran. The mane goal of this research is to present a jihadi command and leadership model based on the soleimani martyr style in the fight against ISIS in Iraq. This research is applied and developmental in terms of type. The method of conducting this research is descriptive-analytical. The statistical community was made up of experts, experts and commanders of the Resistance Movement who had close and long history of cooperation with Martyr Alavi and presence in the Resistance Movement. To collect and complete the research literature and present the conceptual model, the method of library studies was used, and to collect the information of the research model, the method of field research and interview was used. After collecting and categorizing the text of the interviews, they were entered into the Maxqda 2020 software through thematic analysis method. After determining the propositions related to the text of the interviews and by citing and using them, the basic themes were determined and by using the 2020 Maxqda software, while specifying the meaningful, important and relevant units, the basic themes were determined, which includes 370 basic themes. The primary themes were then placed in the process of organizing themes, which reached 11 themes, and by categorizing the organizing themes according to the research topic, the overarching themes were determined into four themes and based on the overarching themes (dimensions), organizer (component) and basic themes. (index), the final research model was presented.

HWRR element is an instrumented fuel assembly constructed based on JCPOA conceptual design parameters for Arak reactor. The in-core experiments of the fuel are carried out in TRR core to evaluate neutronic and thermal-hydraulic parameters using an experimental facility called Open Loop Test Facility (OLTF). Safety analysis of the OLTF anticipated incidents is one of the necessary steps before its implementation. Therefore, three severe anticipated accident scenarios have been simulated, including two LOFA scenarios and the instant post SCRAM cooling by natural circulation. The neutronic calculation has been carried out by MCNPX code to determine fuel rods power and thermal-hydraulic analysis using CFD method. The analysis results show that the clad surface temperature violates coolant saturation temperature and void will arise in both LOFA scenarios. However, both clad and fuel temperatures keep significant margins to their design criteria and fuel rod integrity would be retained completely. The results also show that the coolant temperature remains lower than saturation temperature in the case of decay heat removing via natural cooling scenario.

In the present work, a numerical method is proposed in order to model the subcooled boiling flow in a vertical channel using the Drift Flux Model. The system of nonlinear equations is solved with the fully-implicit scheme using the Jacobian-free Newton–Krylov (JFNK) method. In order to improve the efficiency of the JFNK method and its numerical stability, a semi-implicit physics based preconditioning (PBP) is implemented. Recently, the JFNK method has been widely used to solve large and sparse system of equations. To validate the proposed method, the results were compared with the experimental data, the results of modeling by using the RELAP5 code, and the available numerical results in the literature. It was found that the results corresponding to the present work have a good agreement with those of the other mentioned methods. Also, it was found that the convergence rate of the JFNK method with the PBP is at least 50% higher than the JFNK method, and the void fraction mean absolute percentage error (MAPE) is less than 7.34% over a wide range of flow and pressure

In this study, two methods of nano-particle coating, by boiling and electrophoretic, have been used to investigate the effect of surface modification on the Critical Heat Flux of stainless steel plates. In each of these two methods, the coating was performed for 20, 40, and 60 minutes while other parameters remained constant. The SEM1 and EDS2 images were captured and then the contact angles were measured using the Stadler technique to study the effect of surface properties on Critical Heat Flux.  Finally, the boiling curves of the hydrophilic and superhydrophilic surfaces were obtained and then the Critical Heat Flux (CHF) is determined. The CHF values were compared with the existing experimental data and empirical correlations. It was found that the CHF for nanoparticle coating by pool boiling, is significantly higher than those of electrophoretic coating. Also, a comparison of the present Critical Heat Flux results with those obtained by the empirical correlations that are a function of surface properties showed better agreement

Monitoring the power distribution of reactor core is one of the most challenging issues in the safe operation of nuclear reactors. The Number and arrangement of detectors in a core monitoring system should be determined in a way that maximum amount of information about core states is extracted, while avoiding duplication of similar and correlated measurements. Information theory is the best method to deal with the problem of optimal number and placement of instruments. In this paper, the effects of reactor fuel burn-up on the optimal number and arragement of in-core fixed detectors of Tehran Research Reactor has been investigated using information theory. Comparison the results for the two modes, with and without consideration of the fuel burn-up, shows that by considering fuel burn-up in the placement problem, more information can be extracted from measurements of the detectors. Also, for an equal number of detectors, determined arrangement by considering fuel burn-up, mostly provide larger share of total available information in the data set. Using the optimal arrangement, maximum information can be obtained from minimum number of the detectors, which leads to considerable decrease in the cost of construction, implementation, operation, and maintenance of the in-core detectors for monitoring of neutron flux.

Three fresh fuel rods containing pellets inside zirconium tubes with three different enrichments and different dimensions have been evaluated using neutron radiography examinations at the Tehran Research Reactor. To obtain the information of the internal structure of the fuel rods, two different imaging methods, based on using single coated radiography film and phosphorous imaging plate were applied. The quantitative and qualitative evaluations of the fuel rods have been made using neutronic images of these examinations. In the qualitative evaluation of the images, the internal components of the fuel rod, such as pellets, springs, and end plugs, were well visible. The single coated radiography film had a better spatial resolution rather than the image plate so that the internal details of the rods and the gaps between the pellets were clearly detectable. In the quantitative evaluation, the pellets dimensions, the gaps between pellets, and the dependence of the absorption cross-section with the pellets enrichment have been measured and compared with the manufacturer specifications. This information was in good agreement with each other.

Medium power electron accelerators have many applications in industrial irradiations. In order to meet the industry needs of Iran, several investigations for design and construction of the medium power linear electron accelerator in the VHF band frequency with the energy range of 1 MeV - 5 MeV have been started. The acceleration cavity is one of the important components of this design. In this article the design and construction of the cavity are reported and the results of the simulations and measurements are compered. Mean while the essential parameters, including resonance frequency, quality factor, shunt impedance, figure of merit and transit time factor are evaluated for several configuration of cylindrical cavity using (CST), (HFSS) and (SUPERFISH) codes in order to design an efficient cavity for electron beam with the maximum energy up to 5 MeV and 50 kW power with the lowest power loss. After repeating the simulations and reliability of the results, the designed cavity was constructed and its parameters were measured. The results showed that the measured parameters are in good agreement with simulation results.

Diagnostic methods based on zero power reactor noise theory are very common and widely applicable in kinetic parameters and are also one of the standard diagnosis methods of nuclear reactor cores. Feynman-α method is one of these efficient methods of diagnosis. In this work, this method is employed to measure the prompt neutron decay constant of the Esfahan Light Water Subcritical Reactor (ELWSCR). The ELWSCR is a deep subcritical reactor. Therefore, the prompt neutron decay constant of the core is a large negative quantity. Using an especial data acquisition system, the prompt neutron decay constant of the core, based on the Feynman-α analysis, is estimated to be 3966±88 sec-1. The time window of 100 µs is employed in this investigation. By applying the Rossi-α method, this parameter has alrealy been reported to be 3990±177 sec-1 in references. The comparison shows that our results are in a rather good agreement with that estimated by the Rossi-α method within the range of statistical uncertainties.