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العنوان
Parity simulation for nuclear reactors/
الناشر
Tarek Farouk Nagla,
المؤلف
Nagla, Tarek Farouk.
هيئة الاعداد
باحث / طارق فاروق نجلا
tarek_nagla@yahoo.com
مشرف / وصفى عبد الوهاب
مشرف / محمد نجيب حسن على
naguihhalyx@yahoo.com
مناقش / احمد حسن مرعى
مناقش / سيد بهى الدين عبد الحميد
الموضوع
Nuclear Reactors.
تاريخ النشر
1997
عدد الصفحات
vi, 193P.:
اللغة
الإنجليزية
الدرجة
ماجستير
التخصص
الهندسة (متفرقات)
تاريخ الإجازة
1/1/1997
مكان الإجازة
جامعة الاسكندريه - كلية الهندسة - الهندسة النووية والاشعاعية
الفهرس
Only 14 pages are availabe for public view

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from 227

Abstract

The transient response of nuclear power plants can not be easily solved by analytical solutions because it needs complex several simultaneous differential equations. The analysis of transients in nuclear plants combines interrelated treatments of reactor physics, heat transfer, and fluid dynamics, and its complexity nonnally requires use simulation tools, digital computers are used for virtually all such dynamic simulations. However. Digital simulation codes for nuclear systems are costly to develop, costly to use, and may require substantial expertise to apply. A different tool, known as parity simulation, enables simplified user interaction with simulation. It originated in the study of electronic network transients, and its use spread into areas of nuclear interest, such as neutronic and single-phase flow compressible and incompressible and two-phase flow.
‎To model the system, the thennohydraulic equations of the reactor are rephrased in electrical fonn . Kinetically many physical systems obey the same mathematical patterns. When the electrical equations are parity simulated, the variables in the circuit are analogs of the original nuclear variables. The transient solution of these equations is most easily by use parity simulation.
‎This thesis amid to use the electronic circuits simulation for analysis and display the results by utilizing PSPICE (Simulation Program with Integrated Circuit Enfesied) for Electronic Circuit Design., thus one can study the time behavior of (PWR-900Mwe) reactor kinetics and fuel, gap, clad and coolant temperatures and temperature reactivity feedback ( Doppler & Moderator) during a change of control rods moving by step or ramp functions or in case decrease in boron concentration and the effect of several factors such as, gas release in the gap region, increase the clad thickness, and loss of coolant reactor.
‎The values that obtained from electronic model agree with the numerical values obtained by analytical solution and the simulation of EI-Dabaa which is owned by the (NPP A).
‎’Through this study, it is hoped that parity simulations which is faster, easier, accurately measured and more interactive than digital simulation.