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العنوان
Reactor Shielding Calculation/
الناشر
Youssef A. Shatilla,
المؤلف
Shatilla, Youssef A.
هيئة الاعداد
باحث / Youssef Ahmed Shatilla
مشرف / Mohamed S. Nagy
مشرف / M. Abou Mandour
مشرف / Mohamed S. Nagy
الموضوع
Reactor Shielding.
تاريخ النشر
1988 .
عدد الصفحات
71p.:
اللغة
الإنجليزية
الدرجة
ماجستير
التخصص
الهندسة
تاريخ الإجازة
1/1/1988
مكان الإجازة
جامعة الاسكندريه - كلية الهندسة - Nuclear
الفهرس
Only 14 pages are availabe for public view

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from 80

Abstract

It is essential in studying the transport of fast neutrons through certain media to take into consideration the effect of secondary radiations produced in the medium as a result of the different types of interactions of neutrons. The most important of these is the gamma-radiations, mainly produced by- the_ (n, ’Y ), (n,n’’Y),
(n,p ’y ) , (n, -y a ) ... interactions. These’gamma-radiations(n,p ’y ) , (n, -y a ) ... interactions. These’gamma-radiations(n,p ’y ) , (n, -y a ) ... interactions. These’gamma-radiations(n,p ’y ) , (n, -y a ) ... interactions. These’gamma-radiationswill have a large influence in different fields concerning fission reactor-shields, fusion devices, radiation protec¬tion, industrial process analysis, neutron dosimetry, neutron diagnostics and neutron therapy. Ignorance or
inaccurate determination of these secondary radiations may lead to a significant discrepancies between the calculated
physical functions and their actual values.
Most of radiation tramsport calculational methods adopted in nuclear radiations calculations, handle one type of radiations, either neutrons or gammas, at a time. The mathematical model that treats the simultaneous transport of different types of radiation particles has proved to be very difficult because of the vast amount of the needed input nuclear (fata expressed in the form of differential, cross sections and the complexity of the
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