Multiscale reactor core thermal hydraulic analysis method

A multi-scale analysis, thermal-hydraulic technology, applied in special data processing applications, instruments, electrical and digital data processing, etc., it can solve the problem that the sub-channel program analysis is not as fine as CFD analysis, and it cannot analyze the core cell-scale regional flow. Field distribution information, calculation and analysis dependencies, etc., to ensure efficiency, avoid waste, and improve applicability

Active Publication Date: 2018-11-23
HARBIN ENG UNIV
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Problems solved by technology

However, the sub-channel program analysis is not as precise as CFD analysis, and cannot analyze the flow field distribution information in the cell-scale area of ​​the core, and the calculation and analysis depend on the empirical correlation of heat transfer and flow model coefficients

Method used

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  • Multiscale reactor core thermal hydraulic analysis method
  • Multiscale reactor core thermal hydraulic analysis method

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Embodiment Construction

[0038] The following examples describe the present invention in more detail.

[0039] Step 1: Carry out core thermal-hydraulic calculations through the core subchannel analysis program.

[0040] Step 2: Determine the location and area range of the key area of ​​the reactor core. Specific content: analyze the calculation results of the core thermal hydraulic sub-channel program, and screen the high-temperature sub-channel program control body and the number of control bodies for coolant, fuel cladding, and pellets , or the sub-channel control volumes and the number of control volumes corresponding to the large temperature gradient, large flow rate gradient, large pressure gradient and other parameter large gradient areas, and the actual geometric area of ​​the core corresponding to all the selected control volumes is the core core area .

[0041] Step 3: Determine the boundary conditions of the core CFD analysis area, specific content: for the critical area of ​​the core deter...

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Abstract

The invention provides a multiscale reactor core thermal hydraulic analysis method. The method comprises the following steps of: 1, carrying out reactor core thermal hydraulic calculation through a reactor core sub-channel analysis program; 2, determining a position and an area range of a reactor core key area; 3, determining a boundary condition of a reactor core CFD analysis area; 4, carrying out CFD calculation on the reactor core key area; 5, arranging the CFD calculation result ad analyzing states of thermal hydraulic important parameters of the reactor core key area; 6, arranging the CFDcalculation result and optimizing a calculation model and a conservation equation source item of the sub-channel program; 7, updating a thermal hydraulic calculation model and a conservation equationsource item, in the reactor core key area, of the sub-channel program; 8, repeating the steps 1 to 5 via the updated sub-channel program; and 9, comparing important parameter values of the key area in two adjacent key area CFD calculations so as to judge whether convergence is carried out or not. The method is capable of comprehensively ensuring the accuracy and efficiency of thermal hydraulic state prediction for reactor cores.

Description

technical field [0001] The present invention relates to a method for simulating the thermal-hydraulic state of the reactor core of a nuclear power plant, specifically a method for predicting the thermal-hydraulic state of the nuclear power plant reactor core by combining the thermal-hydraulic multi-scale state analysis program of the nuclear power plant reactor core Technical method. Background technique [0002] The safety and economy of nuclear power plants are affected by the technical level of nuclear reactor core thermal hydraulic state prediction. The refined thermal-hydraulic computational fluid dynamics (CFD) program of the reactor core can simulate the heat transfer and flow of the reactor core on a detailed spatial scale. This kind of simulation is conducive to reducing the safety margin, supporting the power increase of the power station and the extension of the fuel cycle, ensuring the safety of the power station, and improving the economy of the power station. ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06F17/50
CPCG06F30/13G06F30/20
Inventor 陈广亮田兆斐张志俭李磊
Owner HARBIN ENG UNIV
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