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Reactor transient physical and thermal full-coupling fine numerical simulation method and system

A numerical simulation and physical thermal technology, applied in CAD numerical modeling, complex mathematical operations, special data processing applications, etc., to improve efficiency and refinement, ensure calculation efficiency and accuracy, and overcome slow convergence.

Active Publication Date: 2021-06-04
NUCLEAR POWER INSTITUTE OF CHINA
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  • Abstract
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  • Claims
  • Application Information

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Problems solved by technology

[0006] In order to solve the problems existing in the existing simulated physical thermal engineering coupling effect simulation technology, the present invention provides a reactor transient physical thermal full coupling fine numerical simulation method

Method used

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  • Reactor transient physical and thermal full-coupling fine numerical simulation method and system
  • Reactor transient physical and thermal full-coupling fine numerical simulation method and system
  • Reactor transient physical and thermal full-coupling fine numerical simulation method and system

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Embodiment 1

[0066] Compared with the traditional physics-thermal-engineering coupling simulation technology, this embodiment proposes a reactor transient physics-thermal-engineering full-coupling precise numerical simulation method, specifically as follows image 3 As shown, the method of this embodiment specifically includes:

[0067] Step S1, establishing a nonlinear equation system for reactor transient physics thermal engineering coupling.

[0068] The set of nonlinear equations set up in this embodiment is:

[0069]

[0070] where f φ (x), f C (x), f Q (x), Respectively, the residual form of the transient neutron diffusion equation, the delayed neutron precursor concentration equation, the flux-power equation, the coolant energy transient equation and the fuel heat conduction transient equation. F(x) is a set of simultaneous transient physics-thermal-engineering coupling calculation equations, x is the solution vector, which are neutron flux, delayed neutron precursor concen...

Embodiment 2

[0154] Based on the above-mentioned embodiment 1, this embodiment also proposes a reactor transient physical thermal fully coupled fine numerical simulation system, the system includes a model building module, an analysis module and an output module;

[0155] The model building block of this embodiment is used to establish the nonlinear equation system of reactor transient physics thermal engineering coupling:

[0156]

[0157] Among them, f φ (x), f C (x), f Q (x), with Respectively, the residual form of the transient neutron diffusion equation, delayed neutron precursor concentration equation, neutron flux-power equation, coolant energy transient equation and fuel heat conduction transient equation; x is the solution vector; The process is the same as that of Embodiment 1 above, and will not be repeated here.

[0158] The analysis module of this embodiment uses the JFNK method to solve the nonlinear equations, and obtains the transient neutron flux, delayed neutron...

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Abstract

The invention discloses a reactor transient physical and thermal full-coupling fine numerical simulation method and system. The method comprises the steps: S1, establishing a nonlinear equation set of reactor transient physical and thermal coupling ; and S2, solving the nonlinear equation set by adopting a JFNK method to obtain the full-core fuel lattice cell level transient neutron flux, delayed neutron precursor concentration, power, coolant temperature and fuel temperature. According to the method, a neutron physical diffusion equation is dispersed by adopting a fine net difference method, a coolant flow heat transfer equation is simulated by adopting a single-channel model, a cylindrical heat conduction equation is dispersed by adopting a finite volume method, a nonlinear equation set for simulating physical and thermal specialty of a reactor is established, and the nonlinear equation set is solved by adopting a JFNK method; and the three-dimensional transient physical and thermal parameters of the full-core fuel lattice cell level are obtained, and the physical and thermal coupling calculation precision of the reactor is improved.

Description

technical field [0001] The invention belongs to the technical field of nuclear reactor core design, and specifically relates to a reactor transient physical thermal fully coupled fine numerical simulation method and system, and a computer-readable storage medium and computer equipment for storing and executing the above method. Background technique [0002] Reactor physics-thermal coupling means that there is an obvious feedback effect between the physical and thermal quantities in the reactor. Specifically, it means that the fission power calculated by the physics major affects the fuel temperature, moderator density and related physical parameters calculated by the thermal engineering major, and the fuel temperature and moderator density calculated by the thermal engineering major will affect the cross-section parameters of the physics major. Thus affecting the fission power calculated by physics majors, this coupling process is shown in the attached figure 1 shown. [0...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06F30/23G06F17/11G06F111/10
CPCG06F30/23G06F17/11G06F2111/10
Inventor 李治刚安萍芦韡杨洪润卢川于颖锐曾辉刘东强胜龙潘俊杰于洋明平洲
Owner NUCLEAR POWER INSTITUTE OF CHINA
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