Analysis of a pressurised water reactor-based nuclear accident using PCTRAN simulator and fuzzy expert system
by Altab Hossain; Intisher Al-Tahmid Omi; Miskat Islam Anika; Jannat Mahal
International Journal of Nuclear Energy Science and Technology (IJNEST), Vol. 14, No. 4, 2020

Abstract: Potential malfunctions in nuclear reactor operation may cause undesirable consequences or accident. Hence, it is important to analyse the influence of different malfunctions such as Loss of Coolant Accident (LOCA) in hot leg, loss of AC power, turbine trip and loss of flow. Therefore, a pressurised water reactor (VVER-1200) based accident analysis has been carried out. Furthermore, a risk analysis using Fuzzy Expert System (FES) is conducted. FES comprises two Fuzzy Inference Systems (FIS) such as FIS-1 and FIS-2. The input parameters of FIS-1 are obtained using the Personal Computer Transient Analyser (PCTRAN). Subsequently, FIS-2 involves the relationship between inputs 'severity' (output of FIS-1) and 'frequency of failure rate for operating days' and the final output 'Risk Level'. During LOCA, for inputs Reactor Coolant System Pressure (RCSP) deviation of 69 bar, average Temperature of Fuel (TAF) deviation of 496.7°C and number of control rods inserted after run-time of 5, the outputs severity and risk level are found to be 84.6% and 91.7% respectively. A similar pattern is found during loss of flow. On the other hand, the level of risk for loss of AC power and turbine trip is found to be 30% and 93.6%, respectively.

Online publication date: Tue, 21-Sep-2021

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