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Evaluation method and evaluation device for wall thickness of nuclear-grade pipeline of in-service nuclear power station

An evaluation method and nuclear power plant technology, applied in the direction of electrical digital data processing, special data processing applications, instruments, etc., can solve problems such as conservative results, achieve the effect of reducing conservatism, wide application range, and avoiding corrective maintenance

Pending Publication Date: 2022-02-11
CHINA NUCLEAR POWER ENG CO LTD
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0002] At present, the inspection and acceptance criteria for the wall thickness of domestic nuclear power plants in service basically follow the pre-service acceptance criteria, and the pre-service acceptance criteria refer to the relevant standards of design and manufacturing specifications. The allowable deviation of the pipeline wall thickness in this standard is actually the manufacturing tolerance of the pipeline. It is applicable to the factory acceptance and pre-service inspection of pipelines. If the pre-service acceptance criteria are continued to be used during the operation phase, the results will be conservative, which will cause unnecessary corrective maintenance

Method used

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  • Evaluation method and evaluation device for wall thickness of nuclear-grade pipeline of in-service nuclear power station
  • Evaluation method and evaluation device for wall thickness of nuclear-grade pipeline of in-service nuclear power station
  • Evaluation method and evaluation device for wall thickness of nuclear-grade pipeline of in-service nuclear power station

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Embodiment 1

[0051] Such as figure 1 , figure 2 As shown, this embodiment discloses a method for evaluating the wall thickness of nuclear-grade pipelines in active nuclear power plants, which includes steps S0-S5:

[0052] S0, predict the wall thickness t of the pipeline at the next in-service inspection according to the current pipeline condition p,min .

[0053] Specifically, step S0 specifically includes: S1, detecting the wall thickness of the pipeline during this in-service inspection, and obtaining the current wall thickness t c ;S2, according to the current wall thickness t c , the wall thickness data of previous in-service inspections, and the evaluation cycle τ of in-service inspections (ie figure 1 evaluation period in ), predicting the wall thickness t of the pipeline at the next in-service inspection p,min , where the in-service inspection and evaluation cycle τ is determined according to the provisions of the nuclear power plant in-service inspection program, for example...

Embodiment 2

[0105] Such as Figure 4 As shown, this embodiment discloses an evaluation device for the wall thickness of a nuclear-grade pipeline in an in-service nuclear power plant, including a prediction module, a first judgment module, a second judgment module, and a third judgment module, wherein:

[0106] Prediction module for predicting the wall thickness t of the pipeline at the next in-service inspection based on the current pipeline condition p,min Specifically, pipelines include butt-welded pipelines, elbows, elbows, tees, branch pipe plugs, coaxial and eccentric joints, such as commonly used in the nuclear power industry. When the wall thickness is obtained, the current wall thickness t is obtained c , and then according to the current wall thickness t c , the wall thickness data of previous in-service inspections, and the in-service inspection evaluation period τ, predict the wall thickness t of the pipeline at the next in-service inspection p,min , where the in-service ins...

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Abstract

The invention discloses an evaluation method for the wall thickness of a nuclear-grade pipeline of an in-service nuclear power station, and the method comprises the steps of predicting the wall thickness tp, min of the pipeline during the next in-service inspection according to the current condition of the pipeline; comparing the predicted wall thickness tp, min during the next in-service inspection with the nominal thickness tnom of the pipeline so as to carry out preliminary evaluation; determining the minimum design wall thickness tmin of the pipeline, and comparing tp, min and tmin; and determining the minimum design wall thickness t correction, min after the pipeline is corrected, and comparing tp, min with t correction, min. The invention further discloses an evaluation device for the wall thickness of the nuclear-grade pipeline of the in-service nuclear power station. According to the invention, the influence of the reduction of the wall thickness of the pipeline on the service strength and the service life of the pipeline can be comprehensively and accurately evaluated, and on the premise of ensuring that the wall thickness meets the service strength requirement, the evaluation conservative degree is reduced, and unnecessary corrective maintenance is avoided.

Description

technical field [0001] The invention relates to the field of nuclear technology, in particular to an evaluation method and an evaluation device for the wall thickness of nuclear-grade pipelines in active nuclear power plants. Background technique [0002] At present, the inspection and acceptance criteria for the wall thickness of domestic nuclear power plants in service basically follow the pre-service acceptance criteria, and the pre-service acceptance criteria refer to the relevant standards of design and manufacturing specifications. The allowable deviation of the pipeline wall thickness in this standard is actually the manufacturing tolerance of the pipeline. It is applicable to the factory acceptance and pre-service inspection of pipelines. If the pre-service acceptance criteria are continued to be used during the operation phase, the results will be conservative and unnecessary corrective maintenance will be caused. Contents of the invention [0003] The technical p...

Claims

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Application Information

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IPC IPC(8): G06F30/17G06F30/20G06F111/10G06F113/14G06F119/08G06F119/14
CPCG06F30/17G06F30/20G06F2111/10G06F2113/14G06F2119/08G06F2119/14
Inventor 李云龙刘景源张磊张步岭王志强焦利辉李红波宋黔杨鑫焱
Owner CHINA NUCLEAR POWER ENG CO LTD
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