Background: Maxillofacial fractures are common and must be radiologically evaluated to detect fractures, to determine their morphology and topography, and to assess adjacent soft-tissue damage.
Aim of Study:The aim of the current study was to evaluate the role of MDCT in diagnosis of: Maxillofacial fractures.Patients and Methods: This prospective cross-sectional study was carried in Radiodiagnosis Department, Zagazig University Hospitals and private center on twenty eight patients complaining from facial trauma with suspected facial fractures referred from Emergency Department, they were 22 males and 6 females, a ages ranged from 17 to 51 years with mean age of 29 years old. Conventional plain radiography and MDCT were performed to all patients.Results: MDCT examination showed that the most common simple maxillofacial fracture was orbital wall fracture (7 patients), the most common complex fractures zygomaticomaxillary complex fracture (5 patients), the most common orbital bony wall fracture was orbital floor fracture (8 patients).
Conclusion:MDCT is the optimal imaging modality for evaluation of maxillofacial fractures, as it can be often visualize complex injuries with a precision unattainable by conventional radiography or clinical examination. Fracture fragments displacement and rotation are easily determined by MDCT and 3D MDCT is the best modality for demonstrating the spatial relationships of fracture fragments in maxillofacial fractures.
The goal of the present work is to demonstrate the effects of adding uranium dioxide (UO2) to deuterium fuel in the fusion-fission hybrid reactions. The effectiveness of applying a reflector surface on the neutron yield in D-D and D-UO2 reactions has been investigated. The neutrons yielded from the fusion reactions were considered as a neutron source for fission reactions. For this purpose, MCNPX and its extension, the MCUNED code, for D-D fusion processes and UO2 fission reactions were used to calculate the neutron yield and the generated power. Using externally evaluated nuclear data libraries, MCUNED is capable of light ion transport. The D (d, n) 3He reaction with 0.25 gm of deuterium and the fission reactions with 0.25 and 1.0 gm of UO2 were utilized. The results showed that the calculated neutron flux from the D-D fusion reaction increased by a considerable amount when applying the reflector surface. Adding 1.0 gm of UO2 to deuterium fuel enhanced neutron flux by 4.95 times on average, outside the source with the reflector surface. The calculated power increased by about 3-folds when 1.0 gm of UO2 was added. Despite the narrow cross section of the D-D reactions used in this study, it was found that utilizing the reflector surface and UO2 or depleted uranium with restrictive high masses may be able to multiply the generated neutrons and the resulting power.
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