PREDICTION OF AP1000’S NUCLEAR REACTOR PRESSURE VESSEL TEMPERATURE DURING NORMAL OPERATION
نویسندگان
چکیده
Modeling of thermal-hydraulic calculations for the AP1000 core to predict reactor pressure vessel (RPV) temperature has been carried out. The reactor’s primary coolant system transfers heat produced in fuel during operation steam generator. Part will also be transferred from and pipe. This paper presents calculation result RPV prediction normal operation. Calculations were performed using COBRA-EN code analyzing thermal hydraulics analytics predicting temperature. These methods out with aim as well at steady state nominal power conditions, function flow, fluctuation conditions. results 3400 MWt (100% generated was assumed) design flow 10% tube plugging (TDF2) 48,443.7 ton/hr, minimum 15.1 MPa, 15.513 17.133 show that outlet is 326.96°C, 327.01°C, 327.22°C, 303.65°C, 303.87°C, 306.67°C, departure nucleate boiling ratio (MDNBR) 3.21, 3.29, 3.01, respectively. During a fixed MWt, pressure, under condition fluctuation, maximum shown 303.87°C.
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ژورنال
عنوان ژورنال: Jurnal teknologi reaktor nuklir Tri Dasa Mega
سال: 2022
ISSN: ['1411-240X', '2527-9963']
DOI: https://doi.org/10.17146/tdm.2022.24.3.6684