Method and device for calculating leakage rate of fuel channel of heavy water reactor nuclear power unit
The invention belongs to the technical field of nuclear power, and particularly relates to a heavy water reactor nuclear power unit fuel channel leakage rate calculation method and device. By comparing the determined change trend of the simulated dew point with the actually measured change trend of...
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Format: | Patent |
Sprache: | chi ; eng |
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Zusammenfassung: | The invention belongs to the technical field of nuclear power, and particularly relates to a heavy water reactor nuclear power unit fuel channel leakage rate calculation method and device. By comparing the determined change trend of the simulated dew point with the actually measured change trend of the dew point of the annular space gas system, the leakage rate of the current fuel channel can be accurately obtained under the condition that the change area of the simulated dew point is matched with the actually measured change trend of the dew point; the method is of great significance in accurately monitoring the change trend of system leakage and guiding the safe operation of a power station.
本公开属于核电技术领域,具体涉及一种重水堆核电机组燃料通道泄漏率计算方法及装置。本公开通过确定出的模拟露点的变化趋势与实际测得的环隙气体系统露点变化趋势进行比较,在模拟露点的变化区域与实际测得的露点变化趋势相匹配的情况下,可以较为准确的得到当前燃料通道的泄漏率,对于准确监视系统泄漏变化趋势,指导电站安全运行具有非常重要的意义。 |
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