Nuclear reactor core physical and thermal coupling simulation method

A technology for nuclear reactors and simulation methods, which is applied in computational models, electrical and digital data processing, and based on specific mathematical models. Calculation accuracy, the effect of reducing workload

Active Publication Date: 2020-07-14
XI AN JIAOTONG UNIV
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Problems solved by technology

Since the stochastic transport method usually adopts the method of constructing entities to describe the computational domain, which is fundamentally different from the unstructured grid ado

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  • Nuclear reactor core physical and thermal coupling simulation method
  • Nuclear reactor core physical and thermal coupling simulation method
  • Nuclear reactor core physical and thermal coupling simulation method

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Embodiment Construction

[0034] The present invention will be described in further detail below in conjunction with the accompanying drawings and specific embodiments.

[0035] The following combination figure 1 Shown flow chart, take the Monte Carlo neutron transport program and computational fluid dynamics program coupling calculation slab type fuel as example, the present invention is described in further detail: hereinafter the Monte Carlo neutron transport program is referred to as The MCNP5 program refers to the computational fluid dynamics program as the Fluent program.

[0036] Step 1: Aiming at the plate-type fuel assembly structure, the geometric modeling software ANSYS DesignModeler, which is the pre-processing software in the Fluent program, is used to establish the geometric model of the fuel assembly, and the thin cladding located between the fuel and the coolant is faithfully described, as shown in figure 2 As shown in Figure a and Figure b; the grid division software ANSYS Meshing pr...

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Abstract

The invention discloses a nuclear reactor core physical and thermal coupling simulation method, which comprises the following steps of: firstly, establishing a computational domain unstructured grid model by adopting Fluent pretreatment software, and then importing the grid model into Fluent to establish an example; extracting grid information and flow field data in a Fluent example by adopting auser-defined function function of Fluent software, and automatically generating an input file required by MCNP5 calculation; controlling MCNP5 to complete calculation of a neutron physical field by means of a user-defined function function of Fluent, analyzing the output file of the MCNP5, and extracting fission power data of a nuclear fuel region; transmitting the fission power into Fluent software and executing calculation; after initial convergence of Fluent calculation, regenerating an MCNP5 input file by using the user-defined function of the Fluent, calling the MCNP5 again to calculate fission power data, and transmitting the fission power data to the Fluent; and repeating the above steps until Fluent is finally converged. According to the invention, physical and thermal coupling canbe conveniently realized, and a foundation is laid for research of a numerical reactor.

Description

technical field [0001] The invention relates to the field of nuclear reactor core design and safety analysis, in particular to a simulation method for nuclear reactor core physics and thermal engineering coupling. Background technique [0002] Reactor neutron physics field and coolant flow field are interdependent and mutually restricted. During the actual operation of the reactor, when the reactor power changes, the core temperature and its distribution also change, resulting in changes in fuel temperature, moderator density, neutron cross section and solubility of soluble boron. Changes in these parameters will lead to changes in the effective value-added factor of the core, and then act on the power of the core. Due to the significant differences in the time scale and space dimension between the neutron physics field and the coolant thermal-hydraulic flow field, and this feedback has significant nonlinear characteristics, artificial assumptions were forced to be introduc...

Claims

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Application Information

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IPC IPC(8): G06F30/28G06F30/27G06N7/00G06F113/08G06F119/08
CPCG06N7/01
Inventor 张大林王心安周磊王式保秋穗正田文喜苏光辉
Owner XI AN JIAOTONG UNIV
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