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العنوان
Study of neutron flux in thermal reactors/
الناشر
Tarek Atared Zaky Fraag,
المؤلف
Fraag, Tarek Atared Zaky.
هيئة الاعداد
باحث / طارق عطارد زكى فرج
الموضوع
Nuclear Engineering.
تاريخ النشر
1987 .
عدد الصفحات
118 P.:
اللغة
الإنجليزية
الدرجة
ماجستير
التخصص
الهندسة (متفرقات)
تاريخ الإجازة
1/1/1978
مكان الإجازة
جامعة الاسكندريه - كلية الهندسة - الهندسة النووية
الفهرس
Only 14 pages are availabe for public view

from 16

from 16

Abstract

In the scope of reactor design , one can devide the physical work into two main parts :a) The method of calculation b) The adjustment of the met>od to be use£ull. for calculations.
The first part is covered by the Americans (code MUFT’
the EnRlish ( code WIMS ) , the Frensh ( code .APOLLO , ..etcTo cover this part in Egypt, and to develop an Egyptian code, we have devided it into two main divisions : the tberma
tion calculations ,which were given by
El-Sherbin (53),and the slowinp;’ down calculations given in this thesi,~;:
The aim of this ”lark is to’ find a method for calculating the slowing down parameters, and the date to be used for
several types of” reactors.
The multigroup treatment is considered
as the preferable method of calculations.In this work.