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IMPROVING BEST ESTIMATION METHOD FOR CALCULATING REACTOR POWER MEASUREMENT DRIFT OF NUCLEAR POWER PLANT

机译:核电站反应堆功率测量漂移的最佳估计方法的改进

摘要

The present invention relates to a method of improving a best estimation for quantifying a thermal output power measurement drift of a nuclear power plant, comprising: (a) analyzing a nuclear reactor thermal output power variation rate in relation to a major operation variable variation rate of a secondary system (turbine cycle); (b) deriving a linear proportion relation equation representing a nuclear reactor thermal output power variation rate corresponding to the analyzed major operation variable variation rate of 1%; (c) setting a representative value for a major operation variable of the secondary system (turbine cycle) at the nuclear reactor thermal output power of 100% and 95% by using the derived linear proportion relation equation; (d) deriving a coefficient of determination (R^2) corresponding to a square of a coefficient of correlation (Correlation) mathematically representing a magnitude of the linear relation between two variates; (e) setting a reference value (Base Line Data) of respective operation variables by using the derived linear proportion relation equation, when the nuclear reactor thermal output power is stabilized; and (f) measuring the operation variables at an estimation time point when it is predicted that a drift occurs in the nuclear reactor thermal output power. According to the present invention, the drift in the nuclear reactor thermal output power is quantified, thereby minimizing a thermal performance loss problem due to an overestimation of the nuclear reactor thermal output power, and resolving a stability problem due to an underestimation of the nuclear reactor thermal output power.
机译:本发明涉及一种改进用于量化核电厂的热输出功率测量漂移的最佳估计的方法,该方法包括:(a)分析与核反应堆的主要运行变量变化率有关的核反应堆热输出功率变化率。二次系统(涡轮循环); (b)推导表示核反应堆热输出功率变化率的线性比例关系方程,该线性比例关系方程对应于所分析的1%的主要运行变量变化率; (c)通过使用推导的线性比例关系方程式来设定在核反应堆热输出功率分别为100%和95%时的二次系统的主要运行变量(涡轮机循环)的代表值; (d)推导对应于数学上表示两个变量之间线性关系的大小的相关系数(Correlation)的平方的确定系数(R ^ 2); (e)当核反应堆的热输出功率稳定时,通过使用导出的线性比例关系方程式来设定各个操作变量的参考值(基线数据); (f)在预测到核反应堆热输出功率发生漂移的估计时间点测量操作变量。根据本发明,量化了核反应堆热输出功率的漂移,从而使由于高估核反应堆热输出功率引起的热性能损失问题最小化,并解决了由于核反应堆的低估引起的稳定性问题。热输出功率。

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