دراسة معاملات التصميم لتدريع مصدر نيتروني

الموضوعات

علوم بحتة وطبيعية

روابط وملفات

التعريف والنوع

رقم الوثيقة

08957e59-20c2-432f-beaf-3c20e80d2e7f

رقم العقد

0

نوع الوسائط

Crawler

نوع المحتوى

الرسائل العلمية

صيغة المصدر

رسائل ماجيستير

نوع الملف

pdf text

أسماء الملفات

1963533_1.pdf

بيانات النشر

ترجمة العنوان

Studying the Parametric Design of Neutron Source Shielding

ألقاب المؤلفين

[{"name_ar":" أحمد قصي حجو","title_ar":"اشراف","title_en":"Supervision"},{"name_ar":"محمود أحمد مارديني","title_ar":"اعداد","title_en":"Preparation"}]

اللغة

Arabic

المصدر والدورية

اسم المصدر

دراسة معاملات التصميم لتدريع مصدر نيتروني

المحتوى والصفحات

عدد الصفحات

113

ترجمة الملخص

At the beginning of this research the methods of prevention of neutrons and principles of radiation protection and the materials used in shielding neutron were identified in addition to the importance of neutron sources and fusion neutron generator D-D especially and the possibility of shielding sources bypolyethylene with a few additions, and to identify the stages of shielding process the source of neutrons and some reference studies for shieldingneutron.Where this research includes five chapters:-Chapter One: We reviewed the discovery of neutrons, their properties, their types according to their energy, to explain the most important sources that produce from them and the most important applications.-Chapter II: have been addressed to the interactions of neutron with material during: Explanation ofmicroscopic interactions, the cross-section microscopic, connection speed -energy of neutrons, types interactions neutrons, subordinate cross-sections of energy, interactions macroscopic, cross-sections macroscopic, free average path and the rate of the reaction, the effects of the moderation on each article, the effects of doublings in whole material, neutron shielding, attenuation of gamma rays, half thickness HVL and thickness ten TVL.-Chapter III: gives information about the neutron detectors through mechanism of detection and types of used detectors.-Chapter IV: includes hardware and tools.-Chapter V: contains the results and discuss the practical measurements, which was conducted in this research:preparing slabs of mix of polyethylene and boric acid with different weight ratios. the shielding characteristics were studied by using a 2.45 MeV neutron beam which proceeded from fusion neutron generator (NSD) whose neutron intensity 1x107n/s. gamma-rays resulting from the interaction this neutronswith previous slabs were also described, were also identified the half and the tenth-value layer of the additional lead shields using for attenuation these rays. It is found that the slabs of polyethylene which contain 15% of boric acid are the appropriate slabs for attenuation neutrons flowed, because two reasons: the first reason that it have less value from half-value layer (HVL). The second reason that because the gamma rays’ intensity (resulting from neutron capture by the boron existing in it) is maximal Which infers the absorption of the largest possible number of neutrons, and it was also found that the half and the tenth-value layer of the additional lead shields are and , respectively, In order to In order to get a better attenuation of gamma rays.

إشراف وإعداد

الإشراف

أحمد قصي حجو

الإعداد

محمود أحمد مارديني

الاقتباسات الببليوغرافية