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العنوان
Neutron transport calculations in nuclear reactors/
الناشر
Laila Ahmed El-Guebaly,
المؤلف
El-Guebaly,Laila Ahmed.
هيئة الاعداد
باحث / ليلي احمد الجبالى
مشرف / M.M.Abbassi
مشرف / M.E.Zein-El-Din
الموضوع
Nuclear Engineering.
تاريخ النشر
1979 .
عدد الصفحات
199p.:
اللغة
الإنجليزية
الدرجة
الدكتوراه
التخصص
الهندسة (متفرقات)
تاريخ الإجازة
1/11/1979
مكان الإجازة
جامعة الاسكندريه - كلية الهندسة - الهندسه النوويه و الاشعاعيه
الفهرس
Only 14 pages are availabe for public view

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Abstract

and energy depe—n-t%dont-F, All the geometrical ml
physical V
lqsical aspects of the problem are contained in matrix elements which accurately determined
A mcri-el which is based en assuming separability in space end time is developed to predict the asympctic time behaviour of -;’_-,he one speed neutron distribution in a rac¬uangular parallelopiped The model is vized to determine
the stable reactor period and the asymptotic decay cons
tant of a pulse model is, used to assess the valid
ity of using diffusion theory to solve Una dependent problems .
A model is developed to solve the rn-Oltigroup k eige¬nvalua p:,-oble21 for a rectangular parallelepiped . The zodel i.,,; based on. the :kernel factorization method anvd emp¬loys an ita--a”.Yive Starting with diffusion
as the initial Suess rapid convergence is obta¬ined The result- %-e compared to those of diffusion