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العنوان
Accident management :
الناشر
Nour El Hoda Gaber Abd El Mottaleb ,
المؤلف
Abd El Mottaleb, Nour El Hoda Gaber
هيئة الاعداد
باحث / نور الهدى جابر عبد المطلب
مشرف / محمد السيد سليمان ناجى
مشرف / محمد نجيب حسن على
naguihhalyx@yahoo.com
مشرف / محمد الشحات
مناقش / احمد مرعى
مناقش / محمد سلطان
الموضوع
Accident managemet . Nuclear safety .
تاريخ النشر
2001
عدد الصفحات
xv,93 P :
اللغة
الإنجليزية
الدرجة
الدكتوراه
التخصص
الهندسة (متفرقات)
تاريخ الإجازة
1/12/2001
مكان الإجازة
جامعة الاسكندريه - كلية الهندسة - الهندسة النووية و الإشعاعية
الفهرس
Only 14 pages are availabe for public view

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Abstract

Accident management is composed or actions taken during the course or an accident by the plant operating and technical staff mainly to prevent core damage. The ultimate objective or accident management is to achieve a long-term sale, stable state for an extended period of time. This thesis presents a new model for accident management scope. using Gena-Fuzzy Controller (GFC) system. Applying GFC one obtains faster operations, more efficient performance, and optimum solution within a limited number or generations. The proposed model mainly depends on selecting some important plant state variables as a gene fur the overall plant state chromosome, Each or these genes has associated ItIZZ)1 level. The main objective or GFC is turning the plant gene from abnormal states to the normal stale by associated control variable using the inference wise fuzzy technique. Simulation or Pressurized Water Reactor Power Plant (I’WR) has been investigated by simulating the following components, namely, the reactor core, steam generator, pressurizer, reactor coolant system, and pumps. Simulation or reactor core is realized by using a computer program to solve the point kinetic equations with temperature feedback. It is important, when starting simulation, to pay attention to a correct problem definition and to choose only those phenomena, which are considered as relevant to the intended use or the model. In this work simulation or nuclear power plant has been developed and tested in order to mitigate different accident scenarios. Four cases have been studied: The first case is normal transients operation due to step positive reactivity insertion. The second case is normal transients operation due to step negative reactivity insertion. The third case is reactivity transients with Anticipated Transient Without Scram (ATWS) due to control rod movement. Finally, the fourth case is reactivity transients with Anticipated Transient Without Scram (ATWS) due to steam llow rate changes. The Gene-Fuzzy Controller «(iFe) model has been applied with change 01’ error in order [0 account to the negative feedback or both lucl and conluut, which enhance the safety characteristic or reactor control system. Also, it has been applied without change 01’ error ignoring the inherent characteristic or the reactor elements.