Post-processing method for numerical simulation calculation result of pressurized water nuclear reactor pressure vessel

Abstract

The invention discloses a post-processing method for a numerical simulation calculation result of a pressurized water nuclear reactor pressure vessel. The post-processing method comprises the following steps: firstly, confirming and grading a flowing phenomenon existing in an existing pressurized water nuclear reactor pressure vessel; respectively establishing three-dimensional geometric models ofan upper chamber and a lower chamber in the pressurized water reactor pressure vessel; using meshing software for meshing the three-dimensional geometric models of the upper chamber and the lower chamber of the pressure vessel, and importing the three-dimensional geometric models into computational fluid mechanics software for numerical simulation calculation; establishing a three-dimensional geometric model of a complete component in the pressure vessel, carrying out mesh generation on the three-dimensional geometric model, and then carrying out simulation calculation; and importing a calculation result into data analysis processing software, performing a series of processing on the result by utilizing a software trajectory tracking function, and generating a required Python script and arequired result picture. According to the method, different types of pressurized water reactor pressure vessel simulation calculation results can be analyzed and processed, different forms of numerical simulation calculation results can be processed with the same method, and a large amount of repeated and redundant work is avoided.

Description

technical field [0001] The invention belongs to the technical field of nuclear reactor pressure vessels, and in particular relates to a method for post-processing numerical simulation calculation results of pressurized water nuclear reactor pressure vessels. Background technique [0002] The reactor pressure vessel of the pressurized water reactor nuclear power plant is an important device in the reactor coolant pressure boundary barrier. Part of the second barrier to leakage. The internal structure of the pressure vessel and the flow of coolant are very complex. The flow phenomena in the pressure vessel affect the safe operation of the nuclear reactor, such as the flow distribution of the core inlet, the outlet temperature distribution, the vibration and abrasion caused by the control rod flow, and the temperature distribution in the hot leg. It is very important to obtain accurate flow field distribution inside the reactor pressure vessel during the safety analysis of the...

AI Technical Summary

Problems solved by technology

The internal structure of the pressure vessel and the flow of coolant are very complex. The flow phenomena in the pressure vessel affect the safe operation of the nuclear reactor, such as the flow distribution of the core inlet, the outlet temperature distribution, the vibration and abrasion caused by the control rod flow, and the temperature distribution in the hot leg. It is very important to obtain accurate flow field distribution inside the reactor pressure vessel during the safety analysis of the PWR, but the existing test and measurement methods cannot deeply reveal the fine structure of the three-dimensional flow of the coolant in the pressure vessel. Three-dimensional flow field for simulation analysis

Because the number of grids of a complete pressure vessel is generally very large, resulting in a large amount of resulting data, the processing will be cumbersome and inefficient, and a large amount of data will also have great requirements on the hardware configuration of the computer, so it is very necessary to Optimize and improve the processing and analysis of data files to improve work efficiency

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