Uncertainty quantifi cation of the power control system of a small PWR with coolant temperature perturbation
The coolant temperature feedback coefficient is an important parameter of reactor core power controlsystem. To study the coolant temperature feedback coefficient influence on the core power controlsystem of small PWR, the core power control system is built with the nonlinear model and fuzzy controlt...
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Published in | Nuclear engineering and technology pp. 2048 - 2054 |
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Main Authors | , , , , , |
Format | Journal Article |
Language | English |
Published |
한국원자력학회
01.06.2022
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Subjects | |
Online Access | Get full text |
ISSN | 1738-5733 2234-358X |
DOI | 10.1016/j.net.2022.01.005 |
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Summary: | The coolant temperature feedback coefficient is an important parameter of reactor core power controlsystem. To study the coolant temperature feedback coefficient influence on the core power controlsystem of small PWR, the core power control system is built with the nonlinear model and fuzzy controltheory. Then, the uncertainty quantification method of reactor core parameters is established based onthe Latin hypercube sampling method and the Bootstrap method. Finally, under the conditions ofreactivity step perturbation and coolant inlet temperature step perturbation, uncertainty analysis for twocases is carried out. The result shows that with fuzzy controller and fuzzy PID controller, the uncertaintyof the coolant temperature feedback coefficient affects the core power control system, and the maximumuncertainties of core relative power, coolant temperature deviation, fuel temperature deviation and totalreactivity are acceptable KCI Citation Count: 0 |
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ISSN: | 1738-5733 2234-358X |
DOI: | 10.1016/j.net.2022.01.005 |