Nuclear power system interdimensional coupling simulation method

Abstract

The invention discloses a nuclear power system interdimensional coupling simulation method which includes the steps: firstly, performing modeling on components of a nuclear power system through different reactor thermal hydraulics analysis programs; secondly, preliminarily calculating a reactor thermal hydraulic system analysis program and a reactor thermal hydraulic sub-channel analysis program according to set initial boundary conditions; thirdly, taking calculation results of the reactor thermal hydraulic system analysis program and the reactor thermal hydraulic sub-channel analysis programas boundary conditions of computational fluid dynamics software to perform calculation; fourthly, taking calculation results acquired in the third step as boundary conditions of the reactor thermal hydraulic system analysis program to calculate thermal hydraulic parameters of next time step reactor; fifthly, taking calculation results acquired in the fourth step as boundary conditions of the thermal hydraulic sub-channel analysis program to calculate thermal hydraulic parameters of a reactor core; sixthly, repeating the third step to the fifth step until full time calculation is completed.

Description

technical field [0001] The invention belongs to the technical field of method inventions, and in particular relates to a nuclear power system cross-dimensional coupling simulation method. Background technique [0002] The reactor system safety analysis program is used in the reactor to simulate the overall behavior of the nuclear power plant system, and has decades of mature experience in use and development. The reactor system safety analysis program uses the control volume partition method to model the actual flow channel, and uses one-dimensional conservation equations to solve the physical fields. This approach cannot obtain important 3D physical field details in some equipment or components of the nuclear power plant system, and it will lead to deviations in the prediction results of the overall system. In order to obtain more accurate results, some reactor system safety analysis programs such as RELAP5, CATHARE, and TRACE have added three-dimensional flow calculation ...

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Problems solved by technology

[0005] It can be seen that although researchers have developed many computer programs for the simulation of thermal-hydraulic phenomena in reactors, there is still no single program that can meet the actual needs at all scales.

The reactor one-dimensional system analysis program can analyze the accident process well, but the physical field parameters in the pressure vessel cannot be obtained; the reactor thermal-hydraulic sub-channel analysis program can be used to simulate the distribution of boron concentration in the reactor core, but in the absence of reliable In the case of the inlet condition parameters, this kind of calculation is of little significance; the computational fluid dynamics (CFD) method can better simulate the three-dimensional migration and diffusion characteristics of boron in the reactor coolant, but due to its large calculation consumption, the current calculation capacity is difficult to meet demand, so this method is generally only used for local simulation

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