A Comprehensive Prediction Method for Wear Growth of Heat Transfer Tubes of Steam Generators in Nuclear Power Plants

Abstract

A method for comprehensively predicting wear growth of steam generator heat transfer tubes in a nuclear power plant relates to the field of steam generator maintenance. The method includes: step S01, a calculation platform acquires calculation data. In step S02, the calculation platform calculates the wear rate, and compares the wear rate with the repair limit value. If it is greater than the repair limit, mark it for maintenance; otherwise, go to step S03. In step S03, the computing platform calculates using the equal-volume growth method to obtain the first predicted depth. In step S04, the calculation platform compares the first depth with the first predicted depth, and if it is smaller, calculates the second predicted depth using the equal-volume growth method, and then calculates the predicted wear rate; otherwise, uses the equal-depth growth method to calculate. In step S05, the calculation platform compares the predicted wear rate with the repair limit value, if it is greater than the repair limit value, it will be marked for early maintenance, otherwise it will not be marked. The present invention can distinguish wear types for prediction, and can use a prediction method closer to the wear situation, and the 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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Problems solved by technology

[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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