CN113177371A - CFD (computational fluid dynamics) accelerated calculation method for sequential reconstruction of reactor core assembly basin flow field - Google Patents

CFD (computational fluid dynamics) accelerated calculation method for sequential reconstruction of reactor core assembly basin flow field Download PDF

Info

Publication number
CN113177371A
CN113177371A CN202110433778.1A CN202110433778A CN113177371A CN 113177371 A CN113177371 A CN 113177371A CN 202110433778 A CN202110433778 A CN 202110433778A CN 113177371 A CN113177371 A CN 113177371A
Authority
CN
China
Prior art keywords
cfd
flow field
component
component domain
field data
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
CN202110433778.1A
Other languages
Chinese (zh)
Inventor
陈广亮
钱浩
李磊
张志俭
田兆斐
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Harbin Engineering University
Original Assignee
Harbin Engineering University
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Harbin Engineering University filed Critical Harbin Engineering University
Priority to CN202110433778.1A priority Critical patent/CN113177371A/en
Publication of CN113177371A publication Critical patent/CN113177371A/en
Pending legal-status Critical Current

Links

Images

Classifications

    • GPHYSICS
    • G06COMPUTING; CALCULATING OR COUNTING
    • G06FELECTRIC DIGITAL DATA PROCESSING
    • G06F30/00Computer-aided design [CAD]
    • G06F30/20Design optimisation, verification or simulation
    • G06F30/28Design optimisation, verification or simulation using fluid dynamics, e.g. using Navier-Stokes equations or computational fluid dynamics [CFD]
    • GPHYSICS
    • G06COMPUTING; CALCULATING OR COUNTING
    • G06FELECTRIC DIGITAL DATA PROCESSING
    • G06F2113/00Details relating to the application field
    • G06F2113/08Fluids
    • GPHYSICS
    • G06COMPUTING; CALCULATING OR COUNTING
    • G06FELECTRIC DIGITAL DATA PROCESSING
    • G06F2119/00Details relating to the type or aim of the analysis or the optimisation
    • G06F2119/14Force analysis or force optimisation, e.g. static or dynamic forces

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Physics & Mathematics (AREA)
  • Theoretical Computer Science (AREA)
  • Mathematical Physics (AREA)
  • Fluid Mechanics (AREA)
  • Mathematical Analysis (AREA)
  • Mathematical Optimization (AREA)
  • Computing Systems (AREA)
  • Pure & Applied Mathematics (AREA)
  • Computer Hardware Design (AREA)
  • Evolutionary Computation (AREA)
  • Geometry (AREA)
  • General Engineering & Computer Science (AREA)
  • Algebra (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention discloses a CFD (computational fluid dynamics) accelerated calculation method for sequential reconstruction of a reactor core assembly basin flow field, which comprises the following steps: sorting the n component domains of the flow field data to be calculated according to the flow rate of the fluid at the inlet of the component domain; performing computational fluid dynamics calculation on the first component domain to obtain final flow field data of the CFD grid; reconstructing the final flow field data of the CFD grid in the first component domain, and taking the reconstruction result as the initial flow field data of the CFD grid in the second component domain; loading a second component domain boundary condition, and performing CFD calculation on the second component domain to obtain final flow field data of a CFD grid; reconstructing the final flow field data of the CFD grid in the ith component domain, and taking the reconstruction result as the initial flow field data of the CFD grid of the (i + 1) th component domain; and loading the boundary condition of the (i + 1) th component domain, and performing CFD calculation on the (i + 1) th component domain to obtain the final flow field data of the CFD grid of the (i + 1) th component domain. According to the invention, the CFD calculation speed of the component is effectively accelerated according to the principle that the flow fields of the components with close flow are closer.

Description

CFD (computational fluid dynamics) accelerated calculation method for sequential reconstruction of reactor core assembly basin flow field
Technical Field
The specification relates to the technical field of reactor cores, in particular to a CFD (computational fluid dynamics) accelerated calculation method for sequential reconstruction of a reactor core assembly basin flow field.
Background
The core of the reactor, also called the active zone, is composed of fuel assemblies arranged in a grid of the core with a certain grid, the fuel assemblies being assembled by various components in a certain grid arrangement, from fuel elements made in a certain shape (plates, rods, tubes) to meet the physical and thermal hydraulic requirements. The safety and the economy of the nuclear power device are influenced by the prediction technical level of the thermal hydraulic state of the core assembly basin of the nuclear reactor, and the reactor core is subjected to fine Computational Fluid Dynamics (CFD) calculation to obtain detailed flow and heat transfer data, so that the safety margin can be reduced, the design and the optimization of the reactor core assembly of the reactor can be better guided, and the economy and the safety of the reactor design are finally improved. The reactor core comprises a large number of fuel rods, the grid quantity determines the accuracy of the capture of the flowing physical characteristics in the CFD calculation, the traditional CFD calculation method of the pressurized water reactor adopts a default initialization scheme for calculation, however, the calculation speed of the pressurized water reactor core assembly cannot be effectively increased by the initial flow field with a low similarity degree, and a large amount of calculation resources and time are consumed for the fine analysis of the pressurized water reactor core.
It is therefore desirable to provide a computational method that significantly reduces the resources and time required for the CFD computation of the reactor core assembly area flow field.
Disclosure of Invention
In order to solve the above technical problem, the embodiments of the present specification are implemented as follows: the invention provides a CFD (computational fluid dynamics) accelerated calculation method for sequential reconstruction of a reactor core assembly basin flow field, which comprises the following steps:
determining inlet fluid flow data of each of n component domains of flow field data to be calculated;
sorting the n component domains according to the inlet fluid flow of the component domains to obtain a sorted component domain set;
performing Computational Fluid Dynamics (CFD) calculation on a first component domain in the component domain set to obtain final flow field data of all CFD meshes in the first component domain;
reconstructing the final flow field data of all CFD grids in the first component domain according to a preset rule, and taking the flow field data obtained after reconstruction as the initial flow field data of all CFD grids in the second component domain in the component domain set; loading the boundary condition of the second component domain based on the initial flow field data of all CFD meshes in the second component domain, and performing CFD calculation on the second component domain to obtain final flow field data of all CFD meshes in the second component domain;
reconstructing the final flow field data of all CFD grids in the ith component domain in the component domain set according to the preset rule, and taking the flow field data obtained after reconstruction as the initial flow field data of all CFD grids in the (i + 1) th component domain; loading the boundary condition of the (i + 1) th component domain based on the initial flow field data of all CFD grids in the (i + 1) th component domain, and performing CFD calculation on the (i + 1) th component domain to obtain the final flow field data of all CFD grids in the (i + 1) th component domain; wherein i is 2, 3.
Preferably, the specific content of the predetermined rule is: for two adjacent component domains with any sequence number in the ordered component domain set, after calculating the final flow field data of the CFD grid in the component domain with a small sequence number, calculating the ratio E of the inlet fluid flow of the component domain with a large sequence number to the inlet fluid flow of the component domain with a small sequence number; and reconstructing initial flow field data of the component domain with the large serial number according to the ratio E and the final flow field data of the CFD grid in the component domain with the small serial number.
Preferably, the specific content of reconstructing the initial flow field data of the component domain with the large serial number according to the ratio E and the final flow field data of the CFD grid in the component domain with the small serial number is as follows:
traversing all CFD grids in the component domain with small sequence numbers, and acquiring flow field data (V) of the CFD grids in the component domain with small sequence numbersjx,Vjy,Vjz) (ii) a Wherein the symbol j represents the sequence number of the CFD mesh in the component domain with the small sequence number, and j is 1, 2.. and N, N represents the total number of the CFD meshes divided for each component domain; the flow field setting of the jth CFD mesh in the component domain with the large serial number is (EV)jx,EVjy,EVjz)。
Preferably, the boundary conditions comprise at least an inlet fluid velocity or an inlet flow rate of the component area.
One embodiment of the present description can achieve the following advantageous effects: the technical scheme of the invention is based on the research of the flow field rule of each component field of the reactor core, the flow fields of all channels of the reactor core component field have the similarity rule and the fact that the flow fields between the component fields with similar inlet fluid flow are more similar, all the component fields to be calculated are sequenced according to the size of the inlet fluid flow, after the flow field of the current component field is calculated, the flow field is taken as initial flow field data for initializing the flow field of the next component field of the current component field, and then CFD calculation is carried out on the next component field of the current component field, so that the technical scheme of the invention can initialize the flow field of the component field at a layer closer to the real data of the flow field of the component field, greatly reduce the times of CFD calculation iteration, reduce the resource consumption for carrying out CFD calculation on the reactor core components, and finally simulate and predict the heat release, heat transfer and flow of the reactor core on a fine spatial scale, the design and optimization of the reactor core assembly are guided, the safety margin is reduced, the power of the nuclear power station is improved, the fuel cycle is prolonged, and the safety and the economical efficiency of the nuclear power are further ensured.
Drawings
In order to more clearly illustrate the embodiments of the present disclosure or the technical solutions in the prior art, the drawings used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only some embodiments described in the present application, and for those skilled in the art, other drawings can be obtained according to the drawings without any creative effort.
Fig. 1 is a schematic flowchart of a CFD accelerated computation method for sequential reconstruction of a reactor core assembly flow field provided in the present specification.
Detailed Description
To make the objects, technical solutions and advantages of one or more embodiments of the present disclosure more apparent, the technical solutions of one or more embodiments of the present disclosure will be described in detail and completely with reference to the specific embodiments of the present disclosure and the accompanying drawings. It is to be understood that the embodiments described are only a few embodiments of the present specification, and not all embodiments. All other embodiments that can be derived by a person skilled in the art from the embodiments given herein without making any creative effort fall within the scope of protection of one or more embodiments of the present specification.
In the following, briefly described in connection with the understanding of the technical solution of the present invention, the reactor core, also called the reactor core area, is composed of fuel assemblies arranged in a core grid with a certain grid, the fuel assemblies being assembled by fuel elements made in certain shapes (plates, rods, tubes) through various components (upper and lower tube holders, grids, control rod guide tubes, etc.) in a certain grid arrangement to meet the physical and thermal hydraulic requirements. The fuel element cladding is a first safety barrier of a pressurized water reactor nuclear power plant and is a core component of a nuclear fission source in a reactor, so that the fuel element cladding containing a fuel core and fission products is an important component with the most rigorous working condition in the reactor and faces high temperature, high pressure and strong neutron irradiation, the outer wall of the cladding is threatened by coolant pressure, scouring, vibration, corrosion and the like, and when the fuel consumption is increased and the power is increased sharply, the hidden troubles are increased. The computational fluid dynamics CFD program calculation of the refined core thermodynamic computation of the reactor core is carried out on the reactor core, the heat release, the heat transfer and the flow of the reactor core can be simulated and predicted on a fine spatial scale, the design and the optimization of reactor core components are guided, the simulation is favorable for reducing the safety margin, the improvement of the power of a nuclear power station and the prolonging of the fuel cycle are supported, and the safety and the economical efficiency of the nuclear power are ensured. The specific application scene of the technical scheme of the invention can be a simulation process of a pressurized water reactor design stage of a specific model, or thermal hydraulic calculation when different working conditions of a pressurized water reactor core which is designed are simulated.
In CFD calculation, the initial field affects not only the convergence of final calculation but also the calculation speed to a large extent, so the initial field setting is particularly important. Specifically, in the field of pressurized water reactor CFD calculation, a conventional pressurized water reactor CFD calculation method adopts a default initialization scheme for calculation, but the initial flow field with a low similarity degree cannot effectively increase the calculation speed of the pressurized water reactor core assembly, so that a large amount of calculation resources and time are consumed for fine analysis of the pressurized water reactor core. Given an initial flow field which is close to the final calculation result, the number of CFD calculation iterations can be effectively reduced, and further the CFD calculation time can be effectively reduced, however, billions of grids are needed for performing fine CFD calculation on a typical reactor core assembly, and the huge number of grids determines that the data volume corresponding to the initial flow field in the CFD calculation of the reactor core assembly is huge, so that great difficulty can be encountered if the setting of the initial flow field calculated by the reactor core assembly is considered from a microscopic perspective.
The invention provides a CFD (computational fluid dynamics) accelerated calculation method for sequentially reconstructing flow fields of core assemblies of a reactor, which can initialize the flow fields of the core assemblies at a layer closer to real data of the flow fields of the core assemblies by using a layer closer to the real data of the flow fields of the core assemblies based on the fact that the flow fields of all channels of the core assemblies have similarity rules and the flow fields of all assemblies with similar inlet fluid flow are more similar, thereby greatly reducing the frequency of CFD calculation iteration and reducing the resource consumption of CFD calculation on the core assemblies.
The technical solutions provided by the embodiments of the present disclosure are described in detail below with reference to the accompanying drawings, and fig. 1 is a schematic flow chart of a CFD accelerated computation method for sequential reconstruction of a reactor core assembly flow field provided by the embodiments of the present disclosure. From the viewpoint of a program, the execution subject of the flow may be a program installed in an application server or an application client.
And step S1, determining the inlet fluid flow data of each of the n component areas of the flow field data to be calculated.
According to engineering requirements, when CFD calculation is performed on component areas in a reactor core, CFD calculation is sometimes required on all component areas in the core, and sometimes only on a part of the component areas in the core assembly, so that the n component areas of the flow field data to be calculated in this step may refer to all component areas in the core or a part of the component areas of which designers pay attention, and the component areas are not necessarily continuously distributed in physical positions.
Specifically, when performing thermal hydraulic calculation on a specific working condition of a designed pressurized water reactor core, the total fluid flow of the upper cavity of the pressurized water reactor under the specific working condition may be obtained, and then the respective inlet fluid flow or flow speed data of n component domains of the flow field to be calculated may be determined by using a flow distribution program for calculation, or by calculating the flow resistance of each component, or by calculating the core subchannel program flow, so as to obtain the respective inlet fluid flow or flow speed data of each component domain in the n component domains. The flow calculation method may be any one of flow distribution program calculation, core subchannel calculation, and core assembly resistance calculation.
And S2, sorting the n component domains according to the inlet fluid flow of the component domains to obtain a sorted component domain set.
In the field of CFD calculation of a reactor core, as stated above, since it is difficult to calculate the initial flow field by considering the core assembly from a microscopic perspective, the prior art mostly adopts a default initialization scheme for calculation, and since the initial flow field set by the default initialization scheme is greatly different from the real physical field, a great deal of calculation resources and time are consumed. Based on the research of the flow field law of the reactor core assembly, the applicant thinks that when the CFD simulation calculation is carried out on the reactor core assembly domain, if the flow law that the flow fields of all channels of the reactor core assembly domain in the real world have the similarity law and the flow law that the flow rate is similar to the flow field between the assemblies with similar flow rates is effectively utilized, the physical law in the real world is organically integrated into the setting of the initial flow field of the assembly domain during the CFD simulation of the reactor core assembly domain, and the initial flow field of each assembly domain in the CFD calculation set by the scheme is more matched with the law of the real world, the calculation speed of the flow field of the reactor core assembly domain can be greatly increased, and the calculation resources consumed in the calculation process are effectively reduced.
Based on the above consideration, in this step, the n component domains of the flow field data to be calculated in the reactor core are sorted according to the inlet fluid flow of the component domains, so as to obtain a sorted component domain set { component domain 1, component domain 2, component domain 3, and … component domain n }. Wherein all n component fields may also be ordered according to the magnitude of the fluid inlet velocity at the fluid inlet of each component field. After the sorting standard is selected, sorting can be performed from large to small according to the sorting standard, and sorting can also be performed from small to large according to the sorting standard.
Step S3, performing Computational Fluid Dynamics (CFD) calculation on a first component domain in the component domain set to obtain final flow field data of all CFD meshes in the first component domain.
In this step, the CFD calculation is performed on the first component domain in the ordered component domain set { component domain 1, component domain 2, component domain 3, … component domain n } obtained in step S2, that is, component domain 1, it should be noted that, when the CFD calculation is performed on the component field 1, the boundary condition of the component field needs to be loaded, and finally, the final flow field data of the component field 1, that is, all CFD meshes in the first component field can be obtained, wherein the boundary condition is an important part in numerical calculation, the problem to be solved has definite solution only after the boundary condition is given, and boundary conditions are closely related to calculation accuracy, calculation convergence, and calculation speed, the boundary conditions refer to values or gradients of given variables on the boundary of the calculation domain, such as inlet velocity, inlet equivalent diameter, turbulence intensity at the inlet, outlet boundary and wall boundary, etc.
Step S4, reconstructing the final flow field data of all CFD meshes in the first component domain according to a predetermined rule, and using the flow field data obtained after reconstruction as the initial flow field data of all CFD meshes in the second component domain in the component domain set; and loading the boundary condition of the second component domain based on the initial flow field data of all CFD meshes in the second component domain, and performing CFD calculation on the second component domain to obtain the final flow field data of all CFD meshes in the second component domain.
In step S3, the flow field data of all CFD meshes in the first module domain are obtained, and as stated above, the flow fields between the module domains with similar flow rates in the pressurized water reactor core are more similar, so in this step, the flow field data of all CFD meshes in the first module domain is used as the initial flow field data when CFD calculation is performed on the second module domain, and then after the boundary conditions of the second module domain are loaded, CFD calculation can be performed on the second module domain, so that the final flow field data of all CFD meshes in the second module domain is obtained.
It should be noted that the purpose of reconstructing the flow field data of all CFD meshes in the first component domain according to the predetermined rule in this step is only to set the initial flow field data of the second component domain having a similar flow rate to the first component domain by using the final flow field data of all CFD meshes in the first component domain calculated in step S3, and the actual flow field data of the first component domain itself should not be changed, thereby causing a calculation error.
The specific content of the predetermined rule in this step is: for two adjacent component domains with any sequence number in the ordered component domain set, calculating the ratio E of the inlet fluid flow of the component domain with the large sequence number to the inlet fluid flow of the component domain with the small sequence number after calculating the final flow field data of the CFD grid in the component domain with the small sequence number; and reconstructing initial flow field data of the component domain with the large serial number according to the ratio E and the final flow field data of the CFD grid in the component domain with the small serial number. The concrete contents are as follows: traversing all CFD grids in the component domain with small sequence numbers, and acquiring flow field data (V) of the CFD grids in the component domain with small sequence numbersjx,Vjy,Vjz) (ii) a Wherein a symbol j represents a sequence number of the CFD mesh in the component domain having a small sequence number, and j is 1,2The total number of (c); thereby setting the flow field of the jth CFD mesh in the component domain with a large serial number to (EV)jx,EVjy,EVjz). The setting mode of sampling is that the applicant finds through experimental research that the flow fields of all channels of the reactor core assembly of the reactor have a similarity rule, and the flow fields between the component domains with similar flow rates are more similar, so that after the final flow field data of the component domain with small sequence number is calculated, the ratio E of the inlet fluid flow of the component domain with larger sequence number adjacent to the component domain with smaller sequence number to the inlet fluid flow of the component domain with smaller sequence number is calculated, and then the initial flow field of the jth CFD grid in the component domain with larger sequence number is set as (EV)jx,EVjy,EVjz) Therefore, CFD calculation can be carried out on the flow field of the stack core assembly with a larger serial number on the basis of being closer to real flow field data, and the calculation speed is greatly improved.
Step S5, according to the preset rule, reconstructing the final flow field data of all CFD grids in the ith component domain in the component domain set, and taking the flow field data obtained after reconstruction as the initial flow field data of all CFD grids in the (i + 1) th component domain; loading the boundary condition of the (i + 1) th component domain based on the initial flow field data of all CFD grids in the (i + 1) th component domain, and performing CFD calculation on the (i + 1) th component domain to obtain the final flow field data of all CFD grids in the (i + 1) th component domain; wherein i is 2, 3.
In steps S3 and S4, the final flow field data of the first component domain is reconstructed to obtain the initial flow field data of the second component domain, and for the remaining third, fourth, and … n component domains that are not subjected to the initial flow field setting and CFD calculation, the initial flow field setting and CFD calculation are also required. In this step, the flow field data of the second component domain is reconstructed, the flow field data obtained after reconstruction is used as the initial flow field data of all CFD meshes in the third component domain, and then CFD calculation can be performed on the third component domain after the boundary condition of the third component domain is loaded, so as to obtain the final flow field data of the CFD meshes in the third component domain. And then reconstructing the final flow field data of all CFD grids in the third component domain, taking the flow field data obtained after reconstruction as the initial flow field data of all CFD grids in the fourth component domain, and processing according to the rule until the final flow field data of all reactor core components is calculated. Namely, after the final flow field data of all CFD meshes in the ith component domain are obtained, the final flow field data of all CFD meshes in the ith component domain are reconstructed, the flow field data obtained after reconstruction is used as the initial flow field data of all CFD meshes in the (i + 1) th component domain, and then the boundary condition of the (i + 1) th component domain is loaded to obtain the final flow field data of the (i + 1) th component domain.
It should also be noted that, in the technical solution of the foregoing embodiment, only the result of performing reconstruction by using the final flow field data of all CFD meshes in the ith component domain is used as the initial flow field data of all CFD meshes in the (i + 1) th component domain, and the flow field data of all CFD meshes in the ith component domain should not be changed, so as to avoid the occurrence of a calculation error.
In the technical scheme described above, when CFD calculation is performed on the ordered component domain set, for two component domains adjacent to each other in all the ordered components, the final flow field data of the component domain with the small label needs to be used as reconstructed basic data to obtain initial flow field data of the component domain with the large label, and then CFD calculation is performed after the boundary conditions of the component domain with the large label are loaded to obtain final flow field data of the component domain with the large label. Thus, from a serial and parallel perspective of computation, the foregoing solution is essentially serial computation.
With the development of computer hardware technology, the CPU of the existing computer is basically multi-kernel, meanwhile, the distributed computing technology is developed rapidly, and if the powerful computing power of the multi-kernel computer or the distributed computing technology can be fully utilized, the computing speed of the reactor core assembly flow field by using the CFD technology can be further accelerated in the technical scheme of the invention. Based on the above, all n component domains of the flow field data to be calculated can be grouped, each group comprises a plurality of component domains, the grouping principle is that the inlet fluid flow of the component domains in each group is as close as possible, namely, the component domains with the close inlet fluid flow are divided into a group, and then the reactor core component domains in each group are respectively sequenced according to the inlet fluid flow. Then, according to the method, the CFD calculation is performed for each group, and since the initial field data is needed when performing the CFD calculation for the reactor core, one initial flow field data should be provided for each group of reactor core component regions. In a concrete implementation angle, a reactor core component domain flow field database can be established in advance, and the flow field database at least comprises a CFD calculation result of a flow field of a basic component domain and is used for initializing the flow fields of the component domains with the label 1 in each group after grouping, so that multiple groups can be calculated in parallel, and the efficiency of CFD calculation on the flow fields of the reactor core component domains is greatly improved in a general angle.
The technical scheme of the invention is based on the research of the flow field rule of each component field of the reactor core, the flow fields of all channels of the reactor core component field have the similarity rule and the fact that the flow fields of all component fields with similar inlet fluid flow are more similar, all the component fields to be calculated are sequenced according to the size of the inlet fluid flow, and after the flow field of the current component field is calculated, the flow field is used as initial flow field data for initializing the flow field of the next component field of the current component field, and then CFD calculation is carried out on the next component field of the current component field. The method can finally obtain the flow field data of the concerned region in the reactor core, thereby simulating and predicting the heat release, heat transfer and flow of the reactor core on a fine spatial scale and guiding the design and optimization of the reactor core assembly. For example, the fluid flow resistance distribution condition of each core component region can be determined based on the obtained final flow field data of each core component region, and then the diameter of the fuel elements during production and manufacturing of the fuel elements and the interval data among the component regions during assembly of the fuel elements can be determined according to the fluid flow resistance distribution condition, so that the flow speed of the fluid among the core components is increased, the heat exchange strength between the fluid and the core components is increased, and the power improvement and the fuel cycle extension of the nuclear power plant are supported. Or according to the technical scheme of the application, the temperature distribution data of the core assembly area can be obtained through calculation, the high-temperature value required to be born by each part in the fuel assembly can be determined based on the temperature distribution data of the core assembly area, the material required to be used by each part in the fuel rod can be determined based on the high-temperature value required to be born by each part in the fuel rod when the fuel rod is produced and manufactured, and the fuel rod is manufactured by the material finally, so that the safety and the economy of nuclear power are ensured.
The above description is not intended to limit the present invention, and various modifications and changes may be made by those skilled in the art. Any modification, equivalent replacement, or improvement made within the spirit and principle of the present invention should be included in the protection scope of the present invention.

Claims (4)

1. A CFD accelerated calculation method for sequential reconstruction of a reactor core assembly flow field is characterized by comprising the following steps:
determining inlet fluid flow data of each of n component domains of flow field data to be calculated;
sorting the n component domains according to the inlet fluid flow of the component domains to obtain a sorted component domain set;
performing Computational Fluid Dynamics (CFD) calculation on a first component domain in the component domain set to obtain final flow field data of all CFD meshes in the first component domain;
reconstructing the final flow field data of all CFD grids in the first component domain according to a preset rule, and taking the flow field data obtained after reconstruction as the initial flow field data of all CFD grids in the second component domain in the component domain set; loading the boundary condition of the second component domain based on the initial flow field data of all CFD meshes in the second component domain, and performing CFD calculation on the second component domain to obtain final flow field data of all CFD meshes in the second component domain;
reconstructing the final flow field data of all CFD grids in the ith component domain in the component domain set according to the preset rule, and taking the flow field data obtained after reconstruction as the initial flow field data of all CFD grids in the (i + 1) th component domain; loading the boundary condition of the (i + 1) th component domain based on the initial flow field data of all CFD grids in the (i + 1) th component domain, and performing CFD calculation on the (i + 1) th component domain to obtain the final flow field data of all CFD grids in the (i + 1) th component domain; wherein i is 2, 3.
2. The method according to claim 1, wherein the specific content of the predetermined rule is: for two adjacent component domains with any sequence number in the ordered component domain set, calculating the ratio E of the inlet flow of the component domain with the large sequence number to the inlet flow of the component domain with the small sequence number after calculating the final flow field data of the CFD grid in the component domain with the small sequence number; and reconstructing initial flow field data of the component domain with the large serial number according to the ratio E and the final flow field data of the CFD grid in the component domain with the small serial number.
3. The method according to claim 2, wherein the specific content of reconstructing the initial flow field data of the component domain with the large serial number according to the ratio E and the final flow field data of the CFD grid in the component domain with the small serial number is as follows:
traversing all CFD grids in the component domain with small sequence numbers, and acquiring flow field data (V) of the CFD grids in the component domain with small sequence numbersjx,Vjy,Vjz) (ii) a Wherein the symbol j represents the sequence number of the CFD mesh in the component domain with the small sequence number, and j is 1, 2.. and N, N represents the total number of the CFD meshes divided for each component domain; the flow field setting of the jth CFD mesh in the component domain with the large serial number is (EV)jx,EVjy,EVjz)。
4. The method of claim 1, the boundary condition comprising at least an inlet fluid velocity or an inlet flow rate of a component domain.
CN202110433778.1A 2021-04-20 2021-04-20 CFD (computational fluid dynamics) accelerated calculation method for sequential reconstruction of reactor core assembly basin flow field Pending CN113177371A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202110433778.1A CN113177371A (en) 2021-04-20 2021-04-20 CFD (computational fluid dynamics) accelerated calculation method for sequential reconstruction of reactor core assembly basin flow field

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202110433778.1A CN113177371A (en) 2021-04-20 2021-04-20 CFD (computational fluid dynamics) accelerated calculation method for sequential reconstruction of reactor core assembly basin flow field

Publications (1)

Publication Number Publication Date
CN113177371A true CN113177371A (en) 2021-07-27

Family

ID=76924279

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202110433778.1A Pending CN113177371A (en) 2021-04-20 2021-04-20 CFD (computational fluid dynamics) accelerated calculation method for sequential reconstruction of reactor core assembly basin flow field

Country Status (1)

Country Link
CN (1) CN113177371A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN115618498A (en) * 2022-11-08 2023-01-17 中国空气动力研究与发展中心计算空气动力研究所 Prediction method, device, equipment and medium for cross-basin flow field of aircraft

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20150294042A1 (en) * 2012-12-27 2015-10-15 Kepco Engineering & Construction Company, Inc. Simulation construction method for the measurement of control rod insertion time
CN108694299A (en) * 2018-07-17 2018-10-23 中国工程物理研究院核物理与化学研究所 Two dimensional finite element neutronics stable state computational methods based on ICEM-CFD
CN108897907A (en) * 2018-05-25 2018-11-27 哈尔滨工程大学 A method of for reactor core thermal-hydraulic distributed parallel computing
CN110705184A (en) * 2019-09-26 2020-01-17 哈尔滨工程大学 Virtual volume force momentum source method for reactor core refinement numerical solution
CN110728072A (en) * 2019-10-23 2020-01-24 中国核动力研究设计院 Method for determining computational fluid mechanics analysis grid size of digital reactor
CN110826178A (en) * 2019-09-29 2020-02-21 哈尔滨工程大学 Rapid CFD calculation method for reactor core assembly basin based on fine flow field reconstruction

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20150294042A1 (en) * 2012-12-27 2015-10-15 Kepco Engineering & Construction Company, Inc. Simulation construction method for the measurement of control rod insertion time
CN108897907A (en) * 2018-05-25 2018-11-27 哈尔滨工程大学 A method of for reactor core thermal-hydraulic distributed parallel computing
CN108694299A (en) * 2018-07-17 2018-10-23 中国工程物理研究院核物理与化学研究所 Two dimensional finite element neutronics stable state computational methods based on ICEM-CFD
CN110705184A (en) * 2019-09-26 2020-01-17 哈尔滨工程大学 Virtual volume force momentum source method for reactor core refinement numerical solution
CN110826178A (en) * 2019-09-29 2020-02-21 哈尔滨工程大学 Rapid CFD calculation method for reactor core assembly basin based on fine flow field reconstruction
CN110728072A (en) * 2019-10-23 2020-01-24 中国核动力研究设计院 Method for determining computational fluid mechanics analysis grid size of digital reactor

Non-Patent Citations (3)

* Cited by examiner, † Cited by third party
Title
GUANGLIANG CHEN等: "Design and analysis of RIF scheme to improve the CFD efficiency of rod-type PWR core", 《NUCLEAR ENGINEERING AND TECHNOLOGY》 *
李萍等: "CFD方法在压水堆安全分析中的应用现状和发展趋势", 《计算机辅助工程》 *
陈广亮: "PWR堆芯性能CFD分析技术研究", 《中国优秀博硕士学位论文全文数据库(博士) 工程科技Ⅱ辑》 *

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN115618498A (en) * 2022-11-08 2023-01-17 中国空气动力研究与发展中心计算空气动力研究所 Prediction method, device, equipment and medium for cross-basin flow field of aircraft

Similar Documents

Publication Publication Date Title
CN109903870B (en) Cross-dimension coupling simulation method for nuclear power system
Chen et al. CFD investigation on thermal-hydraulic behaviors of a wire-wrapped fuel subassembly for sodium-cooled fast reactor
JP5357376B2 (en) Method for determining an unused fuel bundle design for a nuclear reactor core and a nuclear reactor core
KR100763723B1 (en) Computer modelling method for the core of a nuclear reactor
CN112906271B (en) Reactor transient physical thermal full-coupling fine numerical simulation method and system
Khoshahval et al. A new hybrid method for multi-objective fuel management optimization using parallel PSO-SA
JP2023521581A (en) Computer simulation method for boiling water reactor (BWR)
CN112906272B (en) Reactor steady-state physical thermal full-coupling fine numerical simulation method and system
Valtavirta et al. Coupled neutronics–fuel behavior calculations in steady state using the Serpent 2 Monte Carlo code
Long et al. Review of researches on coupled system and CFD codes
Kianpour et al. Optimal design of a VVER-1000 nuclear reactor core with dual cooled annular fuel based on the reactivity temperature coefficients using thermal hydraulic and neutronic analysis by implementing the genetic algorithms
CN115146545A (en) Intelligent analysis method and system for critical steady state parameters of nuclear reactor core
CN113177371A (en) CFD (computational fluid dynamics) accelerated calculation method for sequential reconstruction of reactor core assembly basin flow field
CN108897907A (en) A method of for reactor core thermal-hydraulic distributed parallel computing
Cifuentes et al. Lattice Boltzmann method applied to nuclear reactors—a systematic literature review
Luo et al. Development and application of a multi-physics and multi-scale coupling program for lead-cooled fast reactor
Avramova et al. Improvements and applications of COBRA-TF for stand-alone and coupled LWR safety analyses
Kutiš et al. CFD analysis of downcomer of nuclear reactor VVER 440
CN115169265A (en) Method, system, device and medium for analyzing blending coefficient based on numerical analysis
Marie et al. VVUQ of a thermal-hydraulic multi-scale tool on unprotected loss of flow accident in SFR reactor
Girieud et al. Science Version 2: the most recent capabilities of the Framatome 3-D nuclear code package
CN113657049A (en) Rapid simulation method for heat transfer and flow of main coolant system of pool type sodium-cooled fast reactor
Ge et al. Development and Application of a New High‐Efficiency Sparse Linear System Solver in the Thermal‐Hydraulic System Analysis Code
Zhang et al. Thermal hydraulic review of light water reactor based on subchannel code CTF
Kamiya et al. Development of JAEA advanced multi-physics analysis platform for nuclear systems

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
RJ01 Rejection of invention patent application after publication

Application publication date: 20210727

RJ01 Rejection of invention patent application after publication