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

staff photo

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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Studying of Naturally Occurring Radioactive Materials (NORM) in Oilfield (A/100) South East of Libya

The huge volume of Naturally Occurring Radioactive Materials (NORM) wastes produced annually by the oil and gas industry in Libya deserves the attention of the national environmental protection authority, radioactive waste management and regulatory bodies. An investigation was carried out to find out the concentration of (NORMs) in evaporation ponds sludge in south eastern oilfield (A/100) of Libya. Twenty soil samples were collected from five evaporation ponds sludge. Activity concentrations of 226Ra, 232Th and 40K in soil generated during oil production operations were determined using a gamma spectroscopy system based on High Purity Germanium (HPGe) detector. Concentrations ranged from 83 to 1000 Bq kg–1 for 226Ra, 59 to 315 Bq kg–1 for 232Th and 109 to 304 Bq kg–1 for 40K. To evaluate the radiological effects, radium equivalent activity and external hazard are calculated. The magnitude of these results demonstrates the need of screening oil residues for their radionuclide content in order to decide about possibility of minimize the environmental impact of NORM and their final disposal. Disposal of NORM waste has to be in accordance with national regulations, environmental policy and international agreements and conventions. The researchers recommend limits for clearance and disposal, based on best international practice. arabic 18 English 82
Usama Elghawi (1-2021)
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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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