Determination method, identification system and identification method for nuclear power station new component codes

Abstract

The invention discloses a determination method, an identification system and an identification method for nuclear power station new component codes, and the code determination method comprises the steps: setting A * B types of codes on a nuclear power station new component to carry out an identification test, and determining A1 types of expected sizes and B1 types of expected depth values of the codes; performing an identification test on the A1 * B1 codes, and determining an expected mounting angle of the identification device; the identification device is installed at an expected installation angle, and the following steps are carried out: for A1 * B1 types of codes, an identification test is carried out by taking the deviation angle of the codes relative to the view center of the identification device as a variable, and A2 types of expected sizes and B2 types of expected depth values of the codes are determined; for A2 * B2 types of codes, the deviation angle is used as a variable,an identification device is used for carrying out an identification test on the codes through a first hole of a guide pipe, and A3 types of expected sizes and B3 types of expected depth values of thecodes are determined; and for A3 * B3 types of codes, an identification test is carried out by taking the moving speed of the codes as a variable, and the optimal expected size and the optimal expected depth value of the codes are determined.

Description

technical field [0001] The embodiments of the present invention relate to the technical field of nuclear engineering, in particular to a method for determining codes for new components of nuclear power plants, an identification system and an identification method. Background technique [0002] Various components in a nuclear reactor are important components for maintaining chain reactions and reactor power control. All components have unique numbers, and the transfer and operation of components is very important. In order to ensure the correct operation of the components, it is necessary to identify the component numbers. [0003] However, in the existing pressurized water reactors, fast reactors and other fields, no identification device is installed to automatically judge the component number for the plug-in operation and transportation process of the components, so it is very likely that the components will be damaged due to human error. Incorrect plugging and unplugging...

AI Technical Summary

Problems solved by technology

[0003] However, in the existing pressurized water reactors, fast reactors and other fields, no identification device is installed to automatically judge the component number for the plug-in operation and transportation process of the components, so it is very likely that the components will be damaged due to human error. Incorrect plugging and unplugging and transport errors, resulting in damage and even danger

[0004] The component numbers marked with clear codes have no error correction function, and the reading rate is low. If one digit is blocked or defaced, the entire number cannot be recognized. It is not suitable for automatic reading of component numbers of nuclear power plants.

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