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Beryllium carbide is under investigation as a possible structural or moderator material in fission and fusion systems. While many of the physical properties of beryllium carbide have already been studied, neutronic properties such as the thermal scattering cross-section are not well known. The purpose of this work is to evaluate the scattering cross section of beryllium carbide through quantum mechanical...
A program has been written in Matlab for image segmentation based on user adjustable grayscale thresholding that can be used not only to locate and select important features in a given image but also count the number of pixels in the selection thereby sizing the feature(s) as a fraction of the total area occupied by the image. The program has been validated against ground truth realities of some locally...
This paper presents a description of a computer simulator, namely, FBRSim, which simulates the thermal-hydraulics of fast breeder reactors (FBRs). It was design to be used for learning and research purposes. It simulates the temperature field, the heat transfer rates, and the pressure drop in typical FBR fuel assemblies. Furthermore, it simulates the core inlet and exit temperature and pressure. The...
Large quantities of nuclear waste plutonium have been accumulated in the civilian LWRs and CANDU reactors in form of minor actinides (MAs). Reactor grade plutonium and other transuranium elements can be used as a booster fissile fuel material in form of mixed ThO2/MAO2 fuel in a CANDU fuel bundle in order to assure reactor criticality. Following fuel compositions have been selected for investigations;...
The thorium fuel cycle fissile and fusile breeding in a molten salt and a solid fuel blanket for a system consisting of fusion fuel factories coupled to fission satellites burners, is considered. The use of the thorium cycle in a fusion fission hybrid could bypass the stage of fourth generation fission breeder reactors in that the energy multiplication in the fission island allows the satisfaction...
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