Comprehensive prediction method for wear increase of heat transfer tube of steam generator of nuclear power plant
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A steam generator and comprehensive forecasting technology, applied in forecasting, instrumentation, electrical and digital data processing, etc., can solve problems such as inability to use accurately, inability to distinguish various types of wear, etc., to promote safe, reliable and economical operation, easy to operate and implement , the effect of reducing errors
Active Publication Date: 2021-07-27
SANMEN NUCLEAR POWER CO LTD
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[0005] The present invention overcomes the problem that in the existing pipeline wear prediction, it is impossible to distinguish multiple wear types, and it is impossible to accurately use a prediction method that is closer to the wear situation. Situation Prediction Mode Integrated Method for Prediction of Wear Growth of Nuclear Power Plant Steam Generator Heat Transfer Tubes
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[0068] The following are specific embodiments of the present invention and in conjunction with the accompanying drawings, the technical solutions of the present invention are further described, but the present invention is not limited to these embodiments.
[0069] Such as Figure 1-7 A comprehensive prediction method for wear growth of steam generator heat transfer tubes in a nuclear power plant is shown, which is used to predict the wear occurring in the contact area between the heat transfer tube 1 and the support. Such as figure 2 As shown, anti-vibration strips 2 are arranged between adjacent heat transfer tubes 1 . Such as image 3 As shown, several support plates 3 are arranged outside each heat transfer tube 1 .
[0070] The anti-vibration strip 2 is tangent to the heat transfer tube 1, and the contact wear is a line contact mode, such as Figure 4 As shown, the axial shape of the wear surface at the contact wear point between the heat transfer tube 1 and the anti...
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Abstract
A comprehensive prediction method for wear increase of a heat transfer tube of a nuclear power plant steam generator relates to the field of steam generator maintenance, and comprises the following steps: step S01, a calculation platform obtains calculation data; S02, the calculation platform calculates the wear rate, the wear rate is compared with a repair limit value, if the wear rate is larger than the repair limit value, maintenance marking is conducted, and if not, the step S03 is executed; and step S03, the calculation platform adopts an isovolumetric growth method for calculation to obtain a first prediction depth; S04, the calculation platform compares the first depth with the first predicted depth, if the first depth is smaller than the first predicted depth, a second predicted depth is obtained through calculation by adopting an isovolumetric growth method, then the predicted wear rate is calculated, and otherwise, the predicted wear rate is calculated by adopting an isovolumetric growth method; S05, the calculation platform compares the predicted wear rate with the repair limit value, if the predicted wear rate is larger than the repair limit value, advanced repair marking is carried out, and otherwise, marking is not carried out. According to the method, the wear types can be distinguished for prediction, a prediction mode closer to the wear condition can be used, and prediction is accurate and convenient.
Description
technical field [0001] The invention relates to the field of steam generator maintenance, in particular to a method for comprehensively predicting wear growth of steam generator heat transfer tubes in nuclear power plants. Background technique [0002] As an important part of the pressure boundary of the reactor coolant system, the steam generator heat transfer tube of the pressurized water reactor nuclear power plant accounts for about 60% of the pressure boundary area of the reactor coolant system. The heat transfer tube of the steam generator undertakes many important safety-related functions. It is not only used to maintain the pressure and water content of the primary circuit system, but also the only boundary between the primary circuit and the secondary circuit for heat transfer. It is also used to prevent the primary circuit coolant from It is an important protective barrier for internal radioactive fission products to enter the secondary circuit system. However, ...
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