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Thermal hydraulic multi-scale partition simulation method of nuclear power device main-coolant system

A main coolant, thermal hydraulic technology, applied in design optimization/simulation, special data processing applications, instruments, etc., can solve problems such as large differences in calculation time costs, system flow calculation divergence, pressure calculation oscillations, etc., to achieve guaranteed Partial fine calculation, improve the calculation fineness, and ensure the effect of accuracy

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

If the system is split and modeled in partitions, the voltage regulator will lose its effect on other loops, which will cause the pressure calculation oscillation of each control body, the system flow calculation will diverge, and the system stability will be poor
[0005] (2) The use of different scale models in multiple partitions will lead to great differences in the time step and calculation time cost of each area. If the calculation sequence and convergence conditions are not set properly, it will lead to low simulation efficiency and even calculation divergence.

Method used

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  • Thermal hydraulic multi-scale partition simulation method of nuclear power device main-coolant system
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  • Thermal hydraulic multi-scale partition simulation method of nuclear power device main-coolant system

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Embodiment Construction

[0024] The following examples describe the present invention in more detail.

[0025] combine figure 2 , the implementation steps of the present invention are as follows:

[0026] (1) According to the actual equipment in the system, the calculation area of ​​the main coolant system is divided, including the core pressure vessel calculation area, the steam generator calculation area, the main pump area, the pressurizer area and the pipeline area between the equipment. The calculation area of ​​the core pressure vessel includes the core upper chamber and outlet section area, the core fuel assembly area, the core inlet descent section and the core lower chamber area; the physical boundaries of each partition must coincide and correspond one by one. Specifically, it is implemented like this:

[0027] a. The calculation area of ​​the core pressure vessel takes the pressure vessel inlet and outlet as the equipment boundary, the parameter transfer boundary is set between the upper...

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Abstract

The invention provides a thermal hydraulic multi-scale partition simulation method of a nuclear power device main-coolant system. The method comprises the following steps: (1) performing computation region division on a main coolant system; (2) establishing a mathematic model for each region, realizing system loop multi-scale modelling and compiling a simulation program, wherein the multi-scale model program comprises a thermal hydraulic system program, a thermal hydraulic sub-channel program and a computational fluid dynamics program; (3) establishing a boundary interface scheme and a data transmission scheme of each region; (4) establishing a time step length setting scheme, a data exchange scheme and a convergence judgment setting scheme according to the scale feature of each region; and (5) configuring the main-coolant system multi-scale program distributed parallel computational environment to realize the multi-region combined simulation. The method provided by the invention is suitable for the multi-scale partition modelling combined simulation method of the thermal hydraulic computation of the nuclear power device main coolant system, the precision of the local computation can be guaranteed, and the fastness of the computation can be guaranteed.

Description

technical field [0001] The invention relates to a reactor thermal-hydraulic simulation method, in particular to a thermal-hydraulic simulation method for a main coolant system of a nuclear power plant. Background technique [0002] The main coolant system of a nuclear power plant is the most important system in the primary loop system. It has major equipment such as the reactor core, voltage stabilizer, main pumps for each loop, and steam generators, and is responsible for transferring the heat generated by the core fuel through the coolant. Transfer to the secondary circuit, and ensure that under normal operating conditions, the entire circuit will not be overheated or overpressured. The thermal-hydraulic calculation of the main coolant system is usually divided into three scales: system scale, component scale and local scale, and the corresponding control volume / grid scale decreases in turn. The main coolant system is a closed system loop. In order to ensure the stability...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06F17/50
CPCG06F30/20
Inventor 田兆斐康慧伦张志俭李磊靳玉冠
Owner HARBIN ENG UNIV
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