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العنوان
numerical solutions of the thermalhydraulics -neutron diffusion equations for reactor accident analysis /
المؤلف
Mohamed, doaa gamal mohamed.
هيئة الاعداد
باحث / عاء جمال محمد محمد
مشرف / ممدوح محمد متولي القاضي
مشرف / خالد سيد محمود ابراهيم
مشرف / خالد سيد محمود ابراهيم
الموضوع
alterative methods(mathematis) differential equations - numerical solutions. neutron transport theory.
تاريخ النشر
2012.
عدد الصفحات
102 p. :
اللغة
الإنجليزية
الدرجة
ماجستير
التخصص
الرياضيات
تاريخ الإجازة
1/1/2012
مكان الإجازة
جامعة حلوان - كلية العلوم - الرياضيات
الفهرس
Only 14 pages are availabe for public view

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Abstract

reactor can get permission for working, if we are able to ~ that even a prompt supercritical state can’t result in a vity accident leading to core damage. Thus, we need a uter models simulating this accident. A power excursion ent is stopped only by the feedback through the temperature icients. For this purpose a 3D neutroniclthermalhydraulics -time model has been built for research reactors and the ing equations has been solved numerically. The results y concluded that the reactor is inherently safe for a prompt
vity 1.2$.