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Fuzzy logic-based steam drum control system for startup of a supercritical-fast reactor

Supercritical-fast reactor is cooled by light water at high pressure of 25 MPa. It is included in t he 4th generation of nuclear reactors, and has excellent features in safety and plant efficiency. There is no phase change during the coolant cycle leading to high outlet coolant temperature. Operatio...

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Bibliographic Details
Main Authors: Sutanto, Sutanto, Rachmadewi, Safira, Puspitasari, Ayu Jati
Format: Conference Proceeding
Language:English
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Summary:Supercritical-fast reactor is cooled by light water at high pressure of 25 MPa. It is included in t he 4th generation of nuclear reactors, and has excellent features in safety and plant efficiency. There is no phase change during the coolant cycle leading to high outlet coolant temperature. Operation of the reactor during startup is challenging due to the pressurization process from subcritical pressure to the operating state. During subcritical pressure, a separated cooling system that is composed of a steam drum, a heat exchanger, and a recirculation pump is provided to achieve stable pressurization by adjusting the liquid level of the steam drum at a constant value. This study proposes a fuzzy-based liquid level control system of the steam drum. Two signals of actual water level and change rate of the water level are taken as the inputs. Triangular functions are used for fuzzification, and the Tsukamoto method is used for inference process with an output signal of coolant flow rate dumped from the steam drum. The performance of the control is evaluated by using a startup code of the same reactor used in the previous study. The performance test of the control system shows that the water level can be kept constant as the desired value during the pressurization with a steady-state error of less than 0.02%. It is smaller than that of using a PID-type control system. The safety criterion of temperature at the cladding surface is also evaluated during the pressurization, and it is well below the limit of allowable cladding surface temperature.
ISSN:0094-243X
1551-7616
DOI:10.1063/5.0122318