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العنوان
Artificial Intelligence Techniques for Modeling and Control of Pressurizer System in Nuclear Power Plants /
المؤلف
Sheta, Amal Adel Abou Elfath.
هيئة الاعداد
باحث / أمل عادل أبوالفتح شتا
مشرف / محمد إبراهيم محمود
مشرف / سيد محمد سيد العربى
مشرف / طارق أحمد محمود
الموضوع
Control engineering. Nuclear energy. Artificial intelligence.
تاريخ النشر
2024.
عدد الصفحات
180 p. :
اللغة
الإنجليزية
الدرجة
الدكتوراه
التخصص
هندسة النظم والتحكم
الناشر
تاريخ الإجازة
27/5/2024
مكان الإجازة
جامعة المنوفية - كلية الهندسة الإلكترونية - هندسة الإلكترونيات الصناعية والتحكم
الفهرس
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Abstract

Nuclear Power Plants (NPPs) are indispensable for maintaining a steady
supply of electricity and reducing the need for frequent refuelling interruptions,
constituting a substantial portion of global electricity generation. Among the various
types of NPPs, Pressurized Water Reactors (PWRs) are widely utilized, relying on
robust safety mechanisms for their operation. Within PWRs, the Pressurizer (PZR)
unit holds particular significance, serving crucial functions such as regulating
primary coolant loop pressure, managing coolant temperature, and stabilizing the
reactor during transients or accidents to ensure the integrity of the containment
system. Given the pivotal role of the PZR in PWR systems, there is a critical need to
develop accurate modeling and control techniques. In this context, this thesis aims
to investigate and develop modeling and control techniques specifically tailored for
the PZR, with a special emphasis on leveraging Artificial Intelligence (AI)-based
methods.
Initially, the thesis focuses on developing a mathematical model capable of
accurately forecasting pressure and water level dynamics within the PZR under
normal operation and during load power changes. This model is constructed as a
non-equilibrium three-region model grounded in the principles of thermodynamics,
encompassing mass and energy interactions within the water and steam phases of
the PZR. This model integrates thermodynamic principles and accounts for multiple
factors affecting pressure and temperature. Validation using simulator data
demonstrates its effectiveness. To validate the accuracy of the developed model,
data generated from the Water-Water Energetic Reactor (VVER-1200) simulator, a
widely used simulation platform for nuclear reactors, is utilized for parameter
estimation, verification, and validation, particularly during load power changes.
Comparative analysis with existing models documented in the literature
demonstrates the superior sensitivity and performance of the developed model. To
explore the application of the developed model in control systems, an analytical
Fuzzy Proportional-Integral-Derivative (FPID) controller with various
configurations is designed to regulate and control the pressure and water level of
the PZR system. Stability analysis of the FPID controllers with variable gains is
conducted, and conditions for Bounded-Input Bounded-Output (BIBO) stability
conditions are derived using the small gain theory. Various scenarios are employed
to assess the dynamic response of the applied controllers under different operating conditions. Additionally, performance indices are compared between the developed
intelligent controller and conventional Proportional-Integral-Derivative (PID)
controllers.
Building upon the developed mathematical model, the thesis
explores the application of AI-based techniques, specifically a TakagiSugano-Kang Fuzzy Neural Network (TSKFNN), for predicting pressure
and water level dynamics within the PZR. The identification of the TSKFNN
model involves multiple steps, including structure and parameter
identification. The Fuzzy C-Means (FCM) clustering method is utilized to
separate input data into clusters and obtain rule antecedent parameters,
while kernel ridge regression defines initial rule consequent parameters.
Subsequently, the sliding-window Kernel Recursive Least Squares (KRLS)
algorithm, in conjunction with the gradient method, adapts TSKFNN model
parameters. Utilizing input/output data from the VVER-1200 simulator,
the TSKFNN model is trained, tested, and evaluated, demonstrating its
effectiveness in predicting PZR behaviour. The simulation results further
validate the efficiency of the TSKFNN model, particularly when compared
with existing mathematical models. Furthermore, the thesis delves into
the self-organizing aspect of the TSKFNN model, which enables automatic
adjustment of fuzzy rules based on the complexity of input data.
Simulation results confirm the viability of the self-organized TSKFNN
model for predicting pressure and water level dynamics. Additionally, the
thesis explores the utilization of the self-organized model to identify and
adapt a Controlled Auto Regressive Integrated Moving Average (CARIMA)
model, commonly employed in control approaches such as Generalized
Predictive Control (GPC). This adapted CARIMA model serves as the basis
for designing a GPC controller for the PZR system. Finally, various
scenarios are employed to assess the dynamic response of the designed
GPC controller. Comparative analysis is conducted with other control
methods, including FPID controllers and conventional PID controllers, to
evaluate the effectiveness and superiority of the GPC controller. The
simulation results provide insights into the performance of different
control strategies and underscore the potential of AI-based methods in
enhancing the safety and efficiency of nuclear power plant operations.