Methods, apparatus and equipment for determining the variation in crack width in the containment structure of nuclear power plants
By acquiring the crack width change and core temperature measured by a high-precision displacement sensor, and combining the thermal expansion coefficients and temperature changes of the core and concrete, the actual crack width change is calculated. This solves the problem of inaccurate measurement under the influence of environmental factors, and improves the accuracy and safety of the measurement.
CN117316477BActive Publication Date: 2026-07-17CHINA GENERAL NUCLEAR POWER OPERATION
Patent Information
- Authority / Receiving Office
- CN · China
- Patent Type
- Patents(China)
- Current Assignee / Owner
- CHINA GENERAL NUCLEAR POWER OPERATION
- Filing Date
- 2023-10-27
- Publication Date
- 2026-07-17
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Figure CN117316477B_ABST
Abstract
This application relates to a method, apparatus, computer equipment, storage medium, and computer program product for determining the width change of cracks in the containment structure of a nuclear power plant. The method includes acquiring a first measured width change of the crack as measured by a high-precision displacement sensor and a first core temperature of the high-precision displacement sensor, and acquiring a first concrete temperature on the outer surface of the containment structure at the installation location of the high-precision displacement sensor; determining a first width change caused by the volume change of the core based on the thermal expansion coefficient of the core and the first core temperature; determining a second width change caused by the volume change of the concrete based on the target cracking coefficient and the first concrete temperature; and determining the true width change of the crack based on the first measured width change, the first width change, and the second width change. The method provided in this application enables a more accurate determination of the crack width change caused by the pressure test.
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