كرم محمود حسن الشاذلى
أستاذ
," Modeling and simulation of loss of the ultimate heat sink in a typical material testing reactor"Elsevier,Annals of Nuclear Energy 51, (2013) 156–166
• 2013
معلومات البحث
المؤلفون
Hisham El-Khatiba, Salah El-Din El-Morshedya, Maher.G. Higazy,, Karam El-Shazly
الكلمات المفتاحية
Not Available
المجلة العلمية
Not Available
الناشر
Not Available
المجلد
Not Available
العدد
Not Available
الصفحات
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publication.type
International
رابط البحث
Open Link
المواد المرفقة
Not Available
الملخص
A thermal–hydraulic model has been developed to simulate loss of the ultimate heat sink in a typical material testing reactor (MTR). The model involves three interactively coupled sub-models for reactor core, heat exchanger and cooling tower. The model is validated against PARET code for steady-state operation and verified by the reactor operation records for transients. Then, the model is used to simulate the thermal–hydraulic behavior of the reactor under a loss of the ultimate heat sink event. The simulation is performed for two operation regimes: regime I representing 11 MW power and three cooling tower cells
operated, and regime II representing 22 MW power and six cooling tower cells operated. In regime I, the simulation is performed for 1, 2 and 3 cooling tower cells failed while in regime II, it is performed for 1, 2, 3, 4, 5 and 6 cooling tower cells failed. The simulation is performed under protected conditions where the
safety action called power reduction is triggered by reactor protection system to decrease the reactor power by 20% when the coolant inlet temperature to the core reaches 43 C and scram is triggered if the core inlet temperature reaches 44 C. The model results are analyzed and discussed.
operated, and regime II representing 22 MW power and six cooling tower cells operated. In regime I, the simulation is performed for 1, 2 and 3 cooling tower cells failed while in regime II, it is performed for 1, 2, 3, 4, 5 and 6 cooling tower cells failed. The simulation is performed under protected conditions where the
safety action called power reduction is triggered by reactor protection system to decrease the reactor power by 20% when the coolant inlet temperature to the core reaches 43 C and scram is triggered if the core inlet temperature reaches 44 C. The model results are analyzed and discussed.
