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Transient monitoring method for supporting fatigue monitoring function of nuclear power plant

A technology for fatigue monitoring and nuclear power plants, applied in the field of transient monitoring, can solve problems such as endangering safety, affecting structural bearing capacity, and structural loss of bearing capacity

Active Publication Date: 2020-04-10
SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

The considerable geometric size of the final crack ranges from seriously affecting the load-bearing capacity of the structure to completely losing the load-bearing capacity of the structure, leading to serious consequences that endanger safety

Method used

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Embodiment

[0025] according to figure 1 As shown, the transient monitoring method of the nuclear power plant fatigue monitoring system provided by the present invention comprises the following steps:

[0026] S1. Establish a database, which stores the transient operating condition characteristic parameters corresponding to the expected transient category matching the monitoring object and its associated system, and the stress change process (or time history) caused by each transient category on the monitoring object and other data;

[0027] S2. Identify the transient start and end of the transient caused by the operating conditions (or operating conditions) of the power plant (pipeline components with a high risk of being adversely affected by fatigue) borne by the monitoring object of the power plant, and obtain the basis for a reasonable fatigue analysis Transient changes; and analyze and summarize the characteristic parameters of the transient working conditions of the identified tra...

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Abstract

The invention aims at disclosing a transient monitoring method for supporting a fatigue monitoring function of a nuclear power plant; the start and the end of a transient occurring on a monitored object are automatically identified through real-time measurement data of an original instrument of an instrument control system of the nuclear power plant, and characteristic parameters of the identifiedtransient are concluded; the method is implemented according to a database and comprises the steps: (1) judging that an identified transient belongs to an expected transient category of the monitoredobject or a process system to which the identified transient belongs through comparison of the characteristic parameters, recording the transient category, occurrence frequency and occurrence time, and directly obtaining a stress change time course of the corresponding monitored object from the database through the recorded transient category; and (2) if the identified transient does not belong to any existing category of transient in the database, establishing a new transient category in the database according to the characteristic parameters of the identified transient, obtaining a stress change time course of the monitored object under the action of the transient category through analysis and calculation, and storing the stress change time course into the new transient category of thedatabase to support subsequent completion of fatigue damage assessment of the monitored object.

Description

technical field [0001] The invention relates to a transient monitoring method, in particular to a transient monitoring method for a nuclear power plant supporting the fatigue monitoring function. This transient monitoring method can not only support the fatigue damage analysis and evaluation of the monitoring object, but also can be used, but not limited to, the fatigue crack growth analysis and evaluation of the monitoring object. Background technique [0002] Fatigue is a type of structural damage that results from repeated cycles of stress / strain caused by changes in load and temperature. After repeated cyclic loading and accumulation of a large amount of localized microstructural damage, initial cracks are initiated at the most severely affected locations. Subsequent cyclic loading and / or thermal stress will propagate the crack. The appreciable geometric size of the final crack ranges from seriously affecting the load-bearing capacity of the structure to completely los...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C17/017G06F16/21G06Q10/00G06Q50/06
CPCG21C17/017G06Q10/20G06Q50/06G06F16/21Y02E30/30
Inventor 梁兵兵张旭施伟黄若涛殷海峰沈小要刘畅邓晶晶于泳洋朱睿嵘
Owner SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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