CN112632735B - Nuclear reactor steam generator grid division method - Google Patents
Nuclear reactor steam generator grid division method Download PDFInfo
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Abstract
The invention discloses a nuclear reactor steam generator mesh division method, which comprises the following steps: 1. establishing a fluid domain geometric model of an upper head region, a dryer region, a gravity separation region, a primary steam-water separator region, a secondary side water supply region, a secondary side tube bundle region, a secondary side descending section region, a primary side tube bundle region, a tube plate region and a lower head region of the steam generator according to geometric parameters of the steam generator of the nuclear reactor; 2. adopting a porous medium and a grid marking method to divide a fluid domain geometric model of a dryer area into grids; 3. adopting a porous medium method to divide grids for the fluid domain geometric models of the primary side tube bundle region and the secondary side tube bundle region; 4. adopting a mixed mesh division method to divide meshes of the geometric model of the residual fluid domain; 5. and combining the grid nodes of the interfaces between the adjacent areas to form a grid model of the steam generator. The invention solves the problem that the full-scale numerical simulation of the steam generator cannot be carried out due to the difficulty in full-scale grid division of the steam generator.
Description
Technical Field
The invention belongs to the technical field of method invention, and particularly relates to a nuclear reactor steam generator grid division method.
Background
The steam generator is the junction between the first and second loops in the pressurized water reactor nuclear power plant and is one of the key devices in the reactor coolant system. The steam generator numerical model based on the three-dimensional CFD method can accurately describe the thermal hydraulic state of the steam generator under different working conditions, the heat transfer performance of the steam generator can be optimized by utilizing flow field data obtained by the model, the compactness of equipment is greatly improved, and key calculation input can be provided for chemical corrosion analysis, dirt deposition analysis and flow induced vibration analysis, so that the reliability and the safety of the equipment are improved. The establishment of the grid model is an important step in the numerical simulation process based on the finite volume method and is also a part with larger workload, and the quality of the grid model is directly related to the subsequent calculation precision and calculation efficiency, so that the grid division method for the steam generator is an important research direction. With the increasing capability of computers, computational fluid dynamics is also increasingly applied to various industrial fields, including modeling and analyzing the internal flow fields of various industrial devices with complex geometries. Despite the ever increasing computational scale and complexity, the demands on grid quality are also increasing: not only can the grid division be carried out on the complex geometric structure, but also the grid quality must be ensured within a reasonable range. At present, commercial software which can divide a grid model in the market mainly comprises: gambit, trueGrid, ANSYS ICEM CFD, ANSYS Mesh, hypermesh, and the like. Because the structure of the steam generator is extremely complex, the span range of the geometric dimension is large, and the flow state of the primary and secondary side fluids in the steam generator is complex, the numerical simulation research of the steam generator by the prior art mostly only aims at local areas or only aims at simplified simple geometric models. These models have limitations, and the simulated boundary conditions thereof cannot truly reflect the operating conditions of the steam generator, and to know the thermal hydraulic state of the whole system of the steam generator under a certain operating condition, the whole steam generator member needs to be modeled and analyzed, which needs to be divided based on the whole grid of the steam generator, and the quality and quantity of the divided grid will be a great challenge.
Disclosure of Invention
In order to solve the problems, the invention provides a nuclear reactor steam generator grid dividing method, aiming at the complex geometry of the nuclear reactor steam generator, the method divides the steam generator into a multi-section geometric structure from top to bottom, respectively establishes a fluid domain geometric model of each section, simplifies and divides the fluid domain geometric model by adopting a porous medium method and a grid marking method according to the complexity of a solid structure and the influence of the solid structure on a flow field, then respectively divides grids aiming at the fluid domain geometric models of the rest parts by adopting a mixed grid dividing method, and finally splices all the area grids together through grid splicing surfaces to form a steam generator grid model.
In order to achieve the purpose, the invention adopts the following technical scheme:
a nuclear reactor steam generator meshing method, comprising the steps of:
step 1: acquiring the geometric parameters of a nuclear reactor steam generator structure, wherein different geometric dimensions of each structure in a full-scale range need to be considered; dividing the steam generator into a plurality of sections from top to bottom according to the flow distribution condition of fluid in the steam generator, wherein each section comprises an upper seal head area, a dryer area, a gravity separation area, a primary steam-water separator area, a secondary side water supply area, a secondary side tube bundle area, a secondary side descending section area, a primary side tube bundle area, a tube plate area and a lower seal head area;
and 2, step: dividing hexahedral structured grids aiming at a fluid domain geometric model of a dryer area, neglecting the structure of a drain pipe when dividing the grids, adopting a porous medium to replace a corrugated plate zigzag structure with a complex structure, and neglecting inclined baffles and upper baffle areas in a dryer unit; obtaining coordinate values of each grid unit in the divided grid model, giving a position equation of the inclined baffle to determine the position of the inclined baffle, performing grid unit circulation in the whole dryer area, marking the grid units meeting the position of the inclined baffle as inclined baffle grid areas, and then deleting the inclined baffle grid areas to realize the deflection effect of the part on fluid motion;
and 3, step 3: simplifying the U-shaped tube bundle into a porous medium model with reasonable pressure loss and heat source terms, and respectively dividing grids according to fluid domain geometric models of a primary side tube bundle region and a secondary side tube bundle region;
and 4, step 4: adopting a mixed grid division method to divide a hexahedral structured grid into the fluid domain geometric model of the upper end enclosure region; dividing a hexahedron structured grid for a fluid domain geometric model of a gravity separation area; dividing a tetrahedral unstructured grid for a fluid domain geometric model of a first-level steam-water separator region; neglecting a complex structure of a secondary side water supply ring pipe, directly regarding a secondary side water supply inlet as a wall surface inlet position at the same height, and dividing a hexahedral structured grid for a fluid domain geometric model of a secondary side water supply area; dividing a hexahedral structured grid for a fluid domain geometric model of a secondary side descending section area; dividing a tetrahedral unstructured grid into a fluid domain geometric model of a tube plate area; dividing a hexahedron structured grid for a fluid domain geometric model of a lower seal head area;
and 5: and D, merging the grid nodes of the interfaces between the adjacent regions according to the topological relation established by the interfaces of the fluid domain geometric models of the regions in the step I, and splicing the grids of the regions together to form the nuclear reactor steam generator grid model.
The invention has the following advantages and beneficial effects:
1) The method is suitable for most of the existing grid model dividing tools, such as Gambit, trueGrid, ANSYS ICEM CFD, ANSYS Mesh, hypermesh and the like.
2) The method of the invention is based on a mixed grid dividing means, and realizes grid splicing among different areas through different grid dividing modes of different areas and a grid node merging technology of interfaces among adjacent areas.
3) The invention adopts porous medium and grid marking method, simplifies and divides the fluid domain grid model to obtain the dryer area and the first and second side tube bundle areas, thereby accurately simulating the complex three-dimensional thermal hydraulic phenomenon in the nuclear reactor steam generator.
4) The method is suitable for steam generators of different types and different structural sizes, and has universality and flexibility.
Drawings
FIG. 1 is a flow chart of the present invention.
Detailed Description
The invention is described in further detail below with reference to the following figures and detailed description:
the invention provides a nuclear reactor steam generator meshing method as shown in figure 1, which comprises the following steps:
step 1: acquiring the geometric parameters of the nuclear reactor steam generator structure, wherein different geometric dimensions of each structure in the whole range of the steam generator need to be considered; according to the flow distribution condition of fluid in the steam generator, the steam generator is divided into a plurality of sections from top to bottom, and the sections mainly comprise an upper seal head area, a dryer area, a gravity separation area, a primary steam-water separator area, a secondary side water supply area, a secondary side tube bundle area, a secondary side descending section area, a primary side tube bundle area, a tube plate area and a lower seal head area, establishing a fluid domain geometric model of each section of area according to the obtained structural geometric parameters, introducing the fluid domain geometric models of all the areas into computational fluid dynamics pretreatment software, and establishing a topological relation at an interface of the fluid domain geometric models of all the areas;
and 2, step: dividing hexahedral structured grids aiming at a fluid domain geometric model of a dryer area, neglecting the structure of a drain pipe when dividing the grids, adopting a porous medium to replace a corrugated plate zigzag structure with a complex structure, and neglecting inclined baffles and upper baffle areas in a dryer unit; obtaining coordinate values of each grid unit in the divided grid model, giving a position equation of the inclined baffle to determine the position of the inclined baffle, performing grid unit circulation in the whole dryer area, marking the grid units meeting the position of the inclined baffle as inclined baffle grid areas, and then deleting the inclined baffle grid areas to realize the deflection effect of the part on fluid motion;
and step 3: simplifying the U-shaped tube bundle into a porous medium model with reasonable pressure loss and heat source terms, and respectively dividing grids aiming at fluid domain geometric models of a primary side tube bundle region and a secondary side tube bundle region;
and 4, step 4: dividing a hexahedral structured grid for the fluid domain geometric model of the upper end enclosure region by adopting a mixed grid division method; dividing a hexahedron structured grid for a fluid domain geometric model of a gravity separation area; dividing a tetrahedral unstructured grid into a fluid domain geometric model of a first-stage steam-water separator region; neglecting the complex structure of the secondary side water supply ring pipe, directly regarding a secondary side water supply inlet as a wall surface inlet position at the same height, and dividing a hexahedral structured grid for a fluid domain geometric model of a secondary side water supply area; dividing a hexahedral structured grid for a fluid domain geometric model of a secondary side descending section area; dividing a tetrahedral unstructured grid into a fluid domain geometric model of a tube plate area; dividing a hexahedron structured grid for a fluid domain geometric model of a lower seal head area;
and 5: and D, merging the grid nodes of the interfaces between the adjacent regions according to the topological relation established by the interfaces of the fluid domain geometric models of the regions in the step I, and splicing the grids of the regions together to form the nuclear reactor steam generator grid model.
The above is a detailed description of the present invention with reference to specific preferred embodiments, which should not be construed as limiting the invention, and it will be apparent to those skilled in the art that various changes and modifications can be made therein without departing from the spirit and scope of the invention as defined by the appended claims.
Claims (1)
1. A nuclear reactor steam generator meshing method, characterized by: aiming at the complex geometry of a nuclear reactor steam generator, dividing the steam generator into a multi-section geometric structure from top to bottom, respectively establishing a fluid domain geometric model of each section, simplifying and dividing grids for the fluid domain geometric model by adopting a porous medium method and a grid marking method according to the complexity of a solid structure and the influence of the solid structure on a flow field, then respectively dividing the grids for the fluid domains of the rest other parts by adopting a mixed grid dividing method, and finally splicing the grids of the regions together through grid splicing surfaces to form a steam generator grid model;
the method comprises the following steps:
step 1: acquiring the geometric parameters of a nuclear reactor steam generator structure, wherein different geometric dimensions of each structure in a full-scale range need to be considered; dividing the steam generator into a plurality of sections from top to bottom according to the flow distribution condition of fluid in the steam generator, wherein each section comprises an upper seal head area, a dryer area, a gravity separation area, a primary steam-water separator area, a secondary side water supply area, a secondary side tube bundle area, a secondary side descending section area, a primary side tube bundle area, a tube plate area and a lower seal head area;
step 2: the method comprises the steps that hexahedral structured grids are divided according to a fluid domain geometric model of a dryer area, when the grids are divided, the structure of a drain pipe is ignored, a porous medium is adopted to replace a corrugated plate zigzag structure with a complex structure, and an inclined baffle in a dryer unit and an upper baffle area are ignored; obtaining coordinate values of each grid unit in the divided grid model, giving a position equation of the inclined baffle to determine the position of the inclined baffle, performing grid unit circulation in the whole dryer area, marking the grid units meeting the position of the inclined baffle as inclined baffle grid areas, and deleting the inclined baffle grid areas to realize the deflection effect of the part on fluid motion;
and 3, step 3: simplifying the U-shaped tube bundle into a porous medium model with reasonable pressure loss and heat source terms, and respectively dividing grids aiming at fluid domain geometric models of a primary side tube bundle region and a secondary side tube bundle region;
and 4, step 4: dividing a hexahedral structured grid for the fluid domain geometric model of the upper end enclosure region by adopting a mixed grid division method; dividing a hexahedron structured grid for a fluid domain geometric model of a gravity separation area; dividing a tetrahedral unstructured grid into a fluid domain geometric model of a first-stage steam-water separator region; neglecting the complex structure of the secondary side water supply ring pipe, directly regarding a secondary side water supply inlet as a wall surface inlet position at the same height, and dividing a hexahedral structured grid for a fluid domain geometric model of a secondary side water supply area; dividing a hexahedral structured grid for a fluid domain geometric model of a secondary side descending section area; dividing a tetrahedral unstructured grid into a fluid domain geometric model of a tube plate area; dividing a hexahedron structured grid into a fluid domain geometric model of a lower end enclosure region;
and 5: and D, merging the grid nodes of the interfaces between the adjacent regions according to the topological relation established by the interfaces of the fluid domain geometric models of the regions in the step I, and splicing the grids of the regions together to form the nuclear reactor steam generator grid model.
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