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Primary-secondary loop coupling calculation method for nuclear power system

A secondary loop, nuclear power technology, applied in the field of nuclear reactor systems, can solve problems such as inability to transmit calculation results, inability to obtain simulation results, etc., to facilitate the realization of coupling and modification of calculation models and simulation conditions, to ensure calculation accuracy, and to improve The effect of accuracy

Active Publication Date: 2021-01-15
XI AN JIAOTONG UNIV
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  • Application Information

AI Technical Summary

Problems solved by technology

System analysis programs generally carry out overall one-dimensional modeling of the primary circuit. The steam generator uses a lumped parameter model or a distributed parameter model, and sets the boundary conditions of the part connected to the secondary circuit according to factors such as steam flow and feedwater flow. The calculation results can reflect The flow and heat transfer characteristics of the steam generator under steady state and accident conditions, but for the space with a large free volume inside the steam generator, such as the structure of the inlet chamber, outlet chamber, steam chamber, etc., it cannot be obtained better The simulation results of
Computational fluid dynamics software is limited by calculation conditions and generally only conducts overall three-dimensional modeling of steam generators, using Reynolds-averaged NS model, large eddy simulation, separation vortex and other turbulence solution models, and the boundary conditions use the fitting results of the system analysis program. Passively accept the changes in the working conditions of the primary and secondary circuits, and cannot pass the calculation results back to the system analysis program

Method used

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  • Primary-secondary loop coupling calculation method for nuclear power system
  • Primary-secondary loop coupling calculation method for nuclear power system

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Embodiment Construction

[0020] In the following, the coupling analysis is realized by calling the system analysis program through the user-defined function of the computational fluid dynamics software as an example, and the explicit coupling method and the area division method of overlapping areas are selected, combined with figure 1 Schematic diagram of the coupling process with figure 2 The modeling diagram for further description:

[0021] The invention provides a coupling calculation method for the first and second loops of a nuclear power system, figure 1 A schematic diagram of the coupling process is given. In the figure, the solid line box is the computational domain of the system program, and the dotted line box is the computational fluid dynamics software computational domain. The specific coupling method is as follows:

[0022] Step 1: Use the geometric model building software to conduct three-dimensional modeling of the internal components of the steam generator, ignoring the small struc...

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Abstract

The invention discloses a primary and secondary circuit coupling calculation method for a nuclear power system, which comprises the following steps: 1, establishing a three-dimensional geometric modelof a reactor steam generator, dividing grids, and establishing a nuclear reactor primary and secondary circuit one-dimensional simplified model; 2, setting an initial boundary condition and a computational domain initial state of the geometric model of the steam generator by using computational fluid dynamics software; 3, calculating the steam generator model by calculation fluid dynamics software to obtain a calculation result, and transmitting the calculation result to a system analysis program to serve as a boundary condition of the time step length of the system analysis program; 4, enabling the system analysis program to calculating the primary and secondary loop model to obtain a calculation result, and transmitting the calculation result to the computational fluid dynamics softwareto serve as a boundary condition for next time step length calculation of the computational fluid dynamics software; 5, repeating step 3 and step 4 until the reactor system model completes all-time calculation. Multi-dimensional and full-system high-fidelity coupling analysis of the reactor system is completed.

Description

technical field [0001] The invention belongs to the technical field of nuclear reactor systems, and in particular relates to a coupling calculation method for primary and secondary loops of a nuclear power system. Background technique [0002] The steam generator is an important device connecting the primary and secondary loops in the nuclear reactor system. It has an important function of transferring heat from the primary loop to the secondary loop under normal operation and certain accident conditions. It is the focus of the coupling calculation of the primary and secondary loops. There are two kinds of analysis methods for steam generators: system analysis program and computational fluid dynamics program. System analysis programs generally carry out overall one-dimensional modeling of the primary circuit. The steam generator uses a lumped parameter model or a distributed parameter model, and sets the boundary conditions of the part connected to the secondary circuit acco...

Claims

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Application Information

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IPC IPC(8): G06F30/28G06F30/10G06F30/23G06F113/08G06F119/14
CPCG06F30/28G06F30/10G06F30/23G06F2113/08G06F2119/14
Inventor 王明军霍雨辰余浩田文喜秋穗正苏光辉
Owner XI AN JIAOTONG UNIV
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