The high-level radioactive WASTE will be encapsulated in copper canisters and stored in a deep repository. High power electron beam welding was the only viable method available at that time for welding thick section copper. In recent years, friction stir welding has been replaced with electron beam welding because of the promotion in mechanical properties and corrosion resistance of copper canisters. FSW is used in solid state, therefore residual stresses produced in the weld is less than that of other welding processes which are performed in the molten state. To obtain optimum rotational speed, FSW was carried out in copper plates with a thickness of 4 mm at a constant speed of 25 mm/minute. The temperature distribution indicated a severe increasing of temperature upon increasing the rotational speed from 900 to 1200 rpm. Also, analysis of the metallographic images showed that the grain size in the nugget zone increases by increasing the rotational speed. Vickers hardness test was conducted on the welded samples and the maximum hardness was obtained at a rotational speed of 900 rpm. Results of tensile tests and their comparison with those of the base metal showed that the maximum strength and minimum elongation are achieved at the same rotational speed.

The current study investigates crystallization and phase separation of a borosilicate glass composition in the system Na2O–, CaO–, Al2O3–, B2O3–, SiO2 used for NUCLEAR WASTE immobilization. At first, base glass composition was prepared by mixing and homogenizing of pure raw materials, melting in an alumina crucible and then casting in a stainless steel mold. Mo2O3 was added in constant values of 0. 5, 1. 5, 2. 5, and 3. 5% mole. XRD analysis was carried out to ensure no crystalline phases were formed. Heat treatment was performed at temperature intervals of 620, 650, 680 and 710°, C. To study phase separation creation, SEM analysis was carried out. In the next step, acid leaching of phase-separated glasses was performed. Porosity analysis and measurement of specific surface area by BET were performed on acid-leached samples. The results show all samples demonstrate different amounts of phase separation. Also, the highest specific surface area was related to the sample containing 1. 5% mole Mo2O3 with two acid-washing steps.

In this paper, we have tried to find a solution for quick transfer of NUCLEAR WASTEs from pools of cool water to dry stores to reduce the environmental concerns and financial cost of burying atomic WASTE. Therefore, the rate of heat transfer from atomic WASTE materials to the outer surface of the container should be increased. This can be achieved by covering the bottom of the pool space with conical fins (vertically) embedded in porous medium and allowing natural convection flow of Newtonian nanofluid upon it. In this research, we studied the rate of heat transfer by using such special space. In this study, Heat transfer boundary layer flow in Nano-fluidics shifting from a vertical cone in porous medium, two-dimensional, steady, incompressible and low speed flow have been considered and attempts have been made to obtain analytical solutions for it. The obtained nonlinear ordinary differential equation has been solved through homotopy analysis method (HAM), considering boundary conditions and Nusselt number. Also, Nusselt number, which is an important parameter in heat transfer, is calculated using the obtained analytical solution by HAM. A comparison of the obtained analytical solution with the numerical results represented a remarkable accuracy. The results also indicate that HAM can provide us with a convenient way to control and adjust the convergence region.

WASTE crime is a new topic in the criminal law, which has a significant part of environmental crimes. Environmental crime has a wide range of environmental impacts, The most important of these effects are pollution. In this respect, WASTE crime as an environmental crime can cause extensive pollution. However, some WASTE such as NUCLEAR WASTE, is more dangerous and more polluting. In fact, NUCLEAR WASTE is dangerous to the environment because of its radioactive material. In this context, smuggling and illicit disposal of NUCLEAR WASTE are among the most important aspects of WASTE crime. In fact, the radiation power of NUCLEAR WASTE and its environmental impact have made it necessary to combat smuggling and illicit disposal of NUCLEAR WASTE. In this regard, combating against the aforementioned acts require that the legislative system organizes in a proportionate manner. On this basis, it is appropriate to establish clear and transparent rules for the export, import, and disposal of NUCLEAR WASTE and criminalizing each of these acts of smuggling and the illegal disposal of NUCLEAR WASTE with the creating of proportionate punishments. Therefore, by studying the Iranian and federal legislation of the United States, it was discovered that Iranian legislator, in addition to not creating an updated and integrated regulation on NUCLEAR WASTE management, has not yet to make appropriate criminal responses to the illegal disposal of the WASTEs. On the other hand, the federal legislator of the United States has adopted an appropriate approach to both NUCLEAR WASTE management and the smuggling and illegal disposal of them. Therefore, during this paper, it attempts to study and analyze the criminal laws of Iran and the United States about the smuggling and illicit disposal of NUCLEAR WASTE.

Technetium-99 in NUCLEAR WASTE as one of the toxic and hazardous radioactive pollutants should be quantitatively and qualitatively identified before final disposal. In the present research work, Technetium -99 in the aqueous phase of the concentrated WASTE of Bushehr NUCLEAR power plant was qualified and quantified. To achieve this goal, Cesium-134 and 137 were firstly separated using potassium cobalt hexacyanoferrate(II) adsorbent. Then, tritium was removed using thermal treatment at 60˚C, and finally technetium-99 in this media was purified by removing beta emitter radioisotopes such as cobalt- 60, iron-55, and nickel-63 using precipitation process with iron(III) hydroxide. The samples were qualitatively and quantitatively evaluated using gamma spectrometry and liquid scintillation counter instruments. The results showed that purified Technetium-99 has a high radiochemical purity and other radioisotopes were removed from the media with an efficiency of about 100%. Also, the beta spectrum of the sample was in complete accordance with the beta spectrum of the standard samples. The total yield of the proposed processes using the increase of Technetium-99m tracer to the original sample was equivalent to 80.69%. Taking into account the 93% efficiency of the liquid scintillation counter and the processes yield (80.69%), the specific activity of Technetium-99 was calculated as 10554.13 Bq.L-1.

Recently, scientists are concerned about NUCLEAR WASTE landfill sites. Because salt pans, salt marsh and salt domes are non-porous environment, with no stubble thickness of salt and the plant communities, less humans and animals can be found around them, so it can be used as a NUCLEAR WASTE landfill. In this study, 24 environmental criteria are investigated with emphasis on hydrology, watershed management, geological structure and socio-economic situations that included: slope, drainage density, maximum instantaneous discharge, drainage class and other parameters. Then, the criteria were evaluated using questionnaire and consultation with experts. The lowest and the most important criteria were related to maximum instantaneous discharge and distance from residential areas with 0.031 and 0.052 value, respectively. In ELECTRE model, all options were evaluated by non-ranking relations and in this way, non-effective options were eliminated. At first, by calculating numerical values, all criteria were given in the form of a matrix, which is called decision matrix. Then data of the decision matrix values which are non-scaled and criteria values were entered in the matrix. Thereafter, the effective coordinated and uncoordinated matrixes and consistent matrixes were obtained and finally, final matrix is formed. According to ELECTRE model results, it could be possible to prioritize three salt domes of southwestern Hormozgan for burying NUCLEAR WASTE. Gachin salt dome, with most indices (1), as the most suitable option and Angouran salt dome, a numerical index (0) and Pol salt dome, with an index number (-1), ranked second and third, respectively.

Radioactive WASTEs are special and dangerous WASTEs that must be disposed of in compliance with safety and health standards to prevent their possible risks to human health and the environment. The WASTE from NUCLEAR ships and submarines is among the WASTE that must be properly disposed of. Navy ships are deactivated when their military capability does not justify the cost of ongoing operations. When the decision is made to decommission a NUCLEAR vessel, it must be defueled, and appropriate measures must be taken to dispose of the reactor plant and the remains of the vessel. In this article, the first part discusses the implementation of a program to dispose of these WASTEs. This program involves several steps, defueling the  reactor,  inactivating  theship, demilitarizing components, removing the reactor compartment for land disposal, recycling the remainder of the ship to the maximum extent practical, and disposing of the remaining non-recyclable materials. In the second part of the article, the control and monitoring of locations with NUCLEAR activity are studied to ensure safety, security, and environmental protection, which is of utmost importance. These activities are carried out by various centers and organizations that require expertise and technical knowledge in the NUCLEAR field.