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العنوان
Thermal Hydraulic Analysis Research Reactors Under Steady State and Transient Conditions \
المؤلف
Abou El-Nour, Asmaa Gamal.
هيئة الاعداد
باحث / أسماء جمال مختار أبو النور
مشرف / ابراهيم داخلي عبد الرازق
مشرف / محمد نجيب علي
مشرف / علياء بدوي
alyabadawi@alex.du.eg
مناقش / أحمد محمد المسيري
مناقش / محمد السيد سليمان ناجي
الموضوع
Nuclear Reactors.
تاريخ النشر
2014.
عدد الصفحات
108 p. :
اللغة
الإنجليزية
الدرجة
الدكتوراه
التخصص
الهندسة (متفرقات)
تاريخ الإجازة
1/9/2014
مكان الإجازة
جامعة الاسكندريه - إدارة جامعة الاسكندرية - ادارة كلية الهندسة - الهندسة النووية
الفهرس
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Abstract

The objective of this research is test the creditability, the capability and the sensitivity of RELAP5 code to predict the research reactor behavior in transients. The output results provide benchmark data which was verified against the experimental measurements. The study used RELAP5 to simulate three different reactors, ETRR-2 (Egypt Second Research Reactor) at steady state, LOFT and negative reactivity insertion, RSG-GAS (Indonesia Reactor) in steady state and LOFT, and WWR-SM (Uzbekistan Reactor) at steady state. The output results were then compared with experimental measurements. The chosen reactors have differences and similarities among them in fuel assembly design, operation power, and flow direction inside the core, control assembly design and heat exchanger design. ETRR-2 and RSG-GAS are similar in fuel assembly design (plate type). The WWR-SM reactor has annular fuel type. On the other hand the WWR-SM and RSG-GAS are similar in flow direction (downward) and in heat exchanger design (shell and tube type) but WWR-SM has horizontal one and RSG-GAS has vertical one. All three reactors are different in operation power and in control rod design (ETRR-2 has plate type, RSG-GAS has fork type and WWR-SM has rod type). The RELAP5 results of three reactors in the different situations were close to measurements with a difference less than 7. The WWR-SM was also used to show the capability of RELAP5 to solve the complexity of fuel geometry, and compare its output with another thermal hydraulic code (P ARET) output. The comparison between the two codes shows that RELAP5 solve the geometry complexity ideally with saving more time and effort than the other code. In the end of study, the sensitivity of the RELAP5 code was studied using one reactor (ETRR-2) but in two form. The first had simplifications in the model but the other simulated the whole plant. The output results were compared and showed that the sensitivity of RELAP5 decreases with simplification. In conclusion, this study found that the RELAP5 results were in a good agreement with experimental measurements in some points, and deviated in other points due to unknown of thermocouples position or shortage in initial conditions. However the deviations are still acceptable.