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Reactor primary loop coolant flow field, temperature field and stress field coupling calculation method

A technology of coolant flow and calculation method, which is applied in the field of nuclear power to achieve the effect of ensuring safe and stable operation

Active Publication Date: 2020-06-09
XIAN THERMAL POWER RES INST CO LTD
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Problems solved by technology

However, there is currently no coupled numerical simulation calculation method that can be used to simultaneously study the flow field, temperature field, and stress field distribution of helium in the primary loop pressure vessel including the core, steam generator, and hot gas conduit.

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  • Reactor primary loop coolant flow field, temperature field and stress field coupling calculation method
  • Reactor primary loop coolant flow field, temperature field and stress field coupling calculation method

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Embodiment Construction

[0043] The present invention is described in further detail below in conjunction with accompanying drawing:

[0044] refer tofigure 1 and figure 2 , the reactor primary loop coolant flow field, temperature field and stress field coupling calculation method of the present invention comprises the following steps:

[0045] 1) According to the high temperature gas-cooled reactor core and steam generator drawings, use the CAD modeling tool embedded in cmosol to construct the high temperature gas-cooled reactor core model and steam generator model with the same size as the actual equipment, among which, image 3 is the geometric model of the reactor core, Figure 4 is the geometric model of the steam generator, in which, for the fast convergence of the computational domain, the characteristics of symmetric structures are applied, image 3 The middle geometry is a Mitsubishi prism, and its volume is 1 / 30 of the actual stack volume; Figure 4 The internal heat transfer tube struct...

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Abstract

The invention discloses a reactor primary loop coolant flow field, temperature field and stress field coupling calculation method. The method comprises the following steps: 1) constructing a high-temperature gas cooled reactor core model and a steam generator model with the same size as actual equipment; 2) establishing a computational domain 1, a computational domain 2 and a computational domain3; 3) setting equipment materials and fluid domains in the computational domain 1, the computational domain 2 and the computational domain 3; 4) setting areas and boundary layers of a flow field, a temperature field and a stress field; 5) meshing the flow field, the temperature field and the stress field; 6) adopting a k-epsilon turbulence model in the computational domain 1 and the computationaldomain 3, and adopting a porous medium model in the computational domain 2; 7) obtaining flow field, temperature field and stress field distribution results of the computational domain 1, the computational domain 2 and the computational domain 3, and 8) obtaining optimal operation parameter configuration of the high-temperature gas cooled reactor at different power levels. The method can realize coupling numerical simulation calculation of the coolant flow field, the temperature field and the stress field of a reactor primary loop.

Description

technical field [0001] The invention belongs to the technical field of nuclear power, and relates to a coupling calculation method for a reactor primary circuit coolant flow field, a temperature field and a stress field. Background technique [0002] The primary circuit coolant of the nuclear power plant reactor is used to cool the core of the nuclear reactor, absorb the heat released by the fission of the nuclear fuel in the reactor, control the reaction rate of the reactor, and transfer the heat to the secondary circuit medium to drive the turbogenerator to generate power. During the normal operation of the reactor, the working fluid state parameters of the reactor coolant directly determine the operating state of the reactor core, and are the key parameters for ensuring the safe and stable operation of the nuclear reactor. [0003] The primary circuit system of the nuclear power plant is enclosed in a pressure vessel, which constitutes the pressure boundary of the primary...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G16C10/00G16C20/10
CPCG16C10/00G16C20/10Y02E30/30
Inventor 刘俊峰
Owner XIAN THERMAL POWER RES INST CO LTD
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