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 robust technique for detecting abdominal aortic calcification using dual energy x-ray absorptiometry

BACKGROUND: Abdominal aortic calcification (AAC) is a marker of atherosclerosis and a predictor of subsequent vascular disease. To date, there has been little research into the automatic detection and quantification of AAC. METHODS: In this study, lateral dual energy X-ray absorptiometry (DXA) scans are used to detect AAC; this is possible because of the anatomical position of the abdominal aorta anterior to the lumbar spine. The deformable shape modelling techniques active shape (ASM) and active appearance (AAM) models are used to model the calcified aorta and four vertebrae of the lumbar spine L1-L4. RESULTS: ASM and AAM were trained and tested on 14 DXA images. The shape of both calcified aorta and four lumbar vertebrae were extracted automatically from the DXA scans using combined shape and appearance models. CONCLUSION: ASM and AAM were implemented successfully. The calcified aorta obtained from the DXA scans was segmented using this modelling technique. The next step is to develop a new automated method to quantify the calcification within the aorta. arabic 13 English 89
Karima Elmasri(6-2015)
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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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Monte Carlo modeling of 6 MV photon beam produced by the elekta precise linear accelerator of Tripoli medical center using beamnrc/dosexyznrc

The 6MV photon beam production by the Elekta Line accelerateur of Tripoli of medical center (TMC) was modeled using Beamnrc and Dosexyzne Monte Carlo codes. The Beamnrc code was used to model the accelerator head and generate phase files. The phase space files were then used as input to the Dosexyzne code to simulate octogenarian deth dose and beam profiles. simulation were first stared using nominal provided by the vendor, a field size of 10x10cm2 and Source to surface distance (SSD) of 100 cm. simulation were compared with experimental data and energy tuning procedures were applied to validate the model. Energy tuning procedures indicated that the nominal energy of 6 MV and a FWHM of the Gaussian distribution of the source of 0.35 cm were the optimal energy and FWHM for the model. The depth of maximum dose at 6 MV was found to be 1.5 cm. The percentage relative differences between calculated and experimental Pdd(s) ranged from 0.5% to 3% for field size of 10cm2 and reached a value of 8% at depths greater than 20cm, The model was later used to calculate PDD(s) and beam profile and output factors for different field size ranging from 3x3cm2 to 25x25cm2. Calculated output factors were in good agreement with experimental values (the percentage relative differences ranged from 1% to 4%). (Author) arabic 42 English 152
Karima Elmasri, Tawfik Giaddui(12-2012)
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