قسم الهندسة النووية

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حول قسم الهندسة النووية

تم إنشاء قسم الهندسة النووية كأحد أقسام كلية الهندسة عام 1974م وتم قبول أول دفعة في العام الدراسي 1977م كما شهد عام 1981م تخريج أول دفعة. ويهدف قسم الهندسة النووية وهو القسم الوحيد بالجامعات الليبية إلى إعداد الكفاءات العلمية المؤهلة والقادرة على استيعاب التطورات التي تحدث في مجال العلوم النووية المساهمة في إدخال أساليب التقنية النووية وتطويعها للاستخدامات السلمية في كافة المجالات ذات العلاقة.

شعب القسم: يضم القسم حالياً شعبتين هما:  شعبة الطاقة وتهتم باستخدامات المفاعلات النووية. وشعبة التطبيقات الإشعاعية وتهتم بتطبيقات الإشعاع النووي .

حقائق حول قسم الهندسة النووية

نفتخر بما نقدمه للمجتمع والعالم

9

المنشورات العلمية

12

هيئة التدريس

109

الطلبة

0

الخريجون

من يعمل بـقسم الهندسة النووية

يوجد بـقسم الهندسة النووية أكثر من 12 عضو هيئة تدريس

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د. كريمة محمد علي المصري

منشورات مختارة

بعض المنشورات التي تم نشرها في قسم الهندسة النووية

A Comparative Study Using Monte Carlo Codes for the Simulation of Photons Emitted by the Elekta Sl-25 Linear Accelerator at the Tripoli Medical Center

Abstract: A 6MV and 15MV electron beams produced by the Elekta precise SL-25 linear accelerator at the Tripoli Medical Center (TMC) were modeled using the MCNP-4C code. Firstly the photon beam energies are tuned by comparison to experimental results previously performed at the TMC. Only the beam energy of the 6MV is modified to 6.2MV. Secondly the percent depth dose curves and beam profiles are calculated for the two energies in different field sizes in the water phantom. Matching with experiment is within an acceptable published allowance of 2%. The distances at which the maximum depth dose in the water phantom is reached are calculated as (1.5cm -1.7cm) for the 6.2MV setting and (2.7cm-3cm) for the 15MVsetting.
خديجة عمر بن ابراهيم (2011)
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Determination of Dose Rates from Natural Radionuclides in Porcelain Dental Materials

There are three main aims that make this study particularly important and interesting to radiometric studies. Firstly, it will provides information on the concentration composition of natural and the associated man-made radioactivity of imported dental porcelain materials to be used by most dental laboratories in Great Jamahiriya. Since these materials do not pass radiation inspection tests before their entry or use and there is a large variety of supply source of these dental materials to be used for all dental works on Libyan patients, anomalies can be identified easily. Secondly, the analysis of selective elemental abundance (U, Th, and K ) and dose rate calculations may be used to calculate effective dose rates to dental laboratory technicians and also to the patient who will be using these specific materials. This research project will provide the first results of such measurements and the corresponding average annual effective dose rates equivalent to the patients using these materials and also to the dental technician and doctors work in the various dental laboratories that make use of these materials in their daily work. A total number of 30 dental powder samples were collected from a number of dental laboratories around Tripoli area will be analyzed. In this research project, the results from this preliminary survey regarding Th, U and K elemental concentrations in a wide variety of dental materials by means of high-resolution X-ray spectrometry will be presented. Further results from these investigations concerning activity concentrations and the associated dose rates, effective dose and the committed dose due to the use of these materials are going to be calculated and compared with other published data elsewhereandrecommendationoftheirusewillbederivedaccordingly. arabic 10 English 74
Karima Mohamed Ali Elmasri, Nouri A. Droughi(9-2010)
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Study of Dose Distribution around a PET Facility in a Nuclear Medicine Clinic

Abstract: Modern PET/CT clinics consist of a scanner room housing PET/CT unit and a control area, two or more waiting rooms where patients rest prior to scanning, and a hot lab where doses are prepared. The 511 keV photons from the PET positron emitting isotopes are the source term for the waiting rooms and the hot lab, while both the 511 keV photons and the polyenergtic spectrum of x-rays from the CT unit must be considered in the scanning roomThis study is intended to estimate dose distribution resulting from using a FDG procedure (555 MBq). The dose distribution is evaluated in injection room, waiting room, and scanning room using two methods. The first method is the analytical method whids is based on AAPM report № 108, while in the second method the dose distribution was simulated using the Monte Carlo code EGSXYZnrc .In the Monte Carlo method some parameters such as the optimal number of histories and the cut off energy of the electron are found to have a significant effect on the results. These parameters are tested and those values with less statistical error are adapted for the calculations.A good agreement between the two methods has been achieved. The dose distribution in the uptake room , waitting room and the scanning room appears to be below the annually dose limit and does not exceed 1% at the adjacent areas.
مريومة البهلول القرقني (2009)
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