| 摘要 |
The present invention is related to the efficiency and safety in the operation of reactors in the nuclear industry, for determining in an optimum manner the hidden variable of a reactor that cannot be directly measured with instruments installed in the plant. More particularly, the invention refers to a method using a control algorithm for reducing the uncertainty in the measurement of the refrigerant flow flowing through the core of natural circulation reactors. Unlike boiling water reactors having a forced recirculation of refrigerant where the flow introduced into the core can be directly measured, the reactors using natural circulation cannot do that due to the elimination of the forced recirculation system. The aforesaid characteristic shows that these types of reactors have uncertainty ranges higher than 10% in the determination of the flow, which leads to a less certainty for defining the regions of instability and the regions allowed to be operated. The present invention is in tended to estimate, with a reduced uncertainty range, the refrigerant flow flowing through the core for improving the operative safety and efficiency in the plant. |
