CN113326648B - Cell homogenization constant calculation method and system considering environmental effect and terminal - Google Patents
Cell homogenization constant calculation method and system considering environmental effect and terminal Download PDFInfo
- Publication number
- CN113326648B CN113326648B CN202110671019.9A CN202110671019A CN113326648B CN 113326648 B CN113326648 B CN 113326648B CN 202110671019 A CN202110671019 A CN 202110671019A CN 113326648 B CN113326648 B CN 113326648B
- Authority
- CN
- China
- Prior art keywords
- reactor core
- neutron
- calculation
- cell
- homogenization
- 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.)
- Active
Links
- 238000004364 calculation method Methods 0.000 title claims abstract description 106
- 238000000265 homogenisation Methods 0.000 title claims abstract description 73
- 230000007613 environmental effect Effects 0.000 title claims abstract description 20
- 238000000034 method Methods 0.000 claims abstract description 35
- 230000008569 process Effects 0.000 claims abstract description 15
- 238000012545 processing Methods 0.000 claims abstract description 11
- 239000000446 fuel Substances 0.000 claims description 12
- 230000004907 flux Effects 0.000 claims description 11
- 238000004590 computer program Methods 0.000 claims description 9
- 238000009792 diffusion process Methods 0.000 claims description 7
- 230000006399 behavior Effects 0.000 claims description 5
- 230000004992 fission Effects 0.000 claims description 5
- 230000000712 assembly Effects 0.000 claims description 4
- 238000000429 assembly Methods 0.000 claims description 4
- 238000010276 construction Methods 0.000 claims description 4
- 238000000605 extraction Methods 0.000 claims description 4
- 230000010354 integration Effects 0.000 claims description 4
- 238000010606 normalization Methods 0.000 claims description 3
- 238000012546 transfer Methods 0.000 claims description 3
- 230000004044 response Effects 0.000 claims 1
- 238000013461 design Methods 0.000 abstract description 7
- 238000010586 diagram Methods 0.000 description 9
- 230000006870 function Effects 0.000 description 6
- 238000009826 distribution Methods 0.000 description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 5
- 230000000694 effects Effects 0.000 description 4
- 238000005516 engineering process Methods 0.000 description 4
- 238000011160 research Methods 0.000 description 3
- 238000003860 storage Methods 0.000 description 3
- 230000006872 improvement Effects 0.000 description 2
- 238000001228 spectrum Methods 0.000 description 2
- 238000004458 analytical method Methods 0.000 description 1
- 238000013459 approach Methods 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000012885 constant function Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 230000003287 optical effect Effects 0.000 description 1
- 239000002574 poison Substances 0.000 description 1
- 231100000614 poison Toxicity 0.000 description 1
- 230000009257 reactivity Effects 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G06—COMPUTING; CALCULATING OR COUNTING
- G06F—ELECTRIC DIGITAL DATA PROCESSING
- G06F30/00—Computer-aided design [CAD]
- G06F30/20—Design optimisation, verification or simulation
- G06F30/23—Design optimisation, verification or simulation using finite element methods [FEM] or finite difference methods [FDM]
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Theoretical Computer Science (AREA)
- Computer Hardware Design (AREA)
- Evolutionary Computation (AREA)
- Geometry (AREA)
- General Engineering & Computer Science (AREA)
- General Physics & Mathematics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a method, a system and a terminal for calculating a cell homogenization constant by considering environmental effect, which relate to the field of nuclear reactor core design and reactor physical calculation, and have the technical scheme that: selecting the neutron characteristics of the reactor core according to the characteristic parameter conservation principle between the uniform reactor core calculation and the non-uniform grid calculation; establishing a difference table of the discontinuity factor or the super homogenization factor and the neutron characteristic of the reactor core; performing reactor core rod-by-rod calculation by using equivalent homogenization constants obtained by calculating single-component problems of various types under the condition of total reflection boundary to obtain reactor core neutronics characteristic quantity corresponding to reactor core neutronics characteristics in each grid cell; and carrying out multi-dimensional linear interpolation processing on the neutron characteristic quantity in the reactor core according to the difference table, and accurately calculating to obtain the equivalent homogenization small group constant of the grid cells. The method effectively weakens the influence of the real reactor core environment on the homogenization section, which is not considered by the boundary condition of total reflection in the calculation process of the cell homogenization constant, so that the calculation precision of the reactor core rod by rod is improved.
Description
Technical Field
The invention relates to the field of nuclear reactor core design and reactor physical calculation, in particular to a grid cell homogenization constant calculation method, a grid cell homogenization constant calculation system and a grid cell homogenization constant calculation terminal considering environmental effects.
Background
The core of a pressurized water reactor is generally composed of hundreds of fuel assemblies and complicated structural materials such as enclosing plates/reflecting layers and the like. Each fuel assembly contains hundreds of different types of cells, such as fuel rod cells, burnable poison rod cells, water tunnel cells, and the like. On the other hand, the energy distribution of neutrons in the nuclear reactor core ranges from 10MeV for fission neutrons to 10MeV for thermal neutrons-2A wide range of eV. These two factors make direct calculation of a well-described reactor expensive and time consuming. The method is limited by the level of calculation conditions and calculation methods, and the three-dimensional full-core non-uniform one-step calculation cannot be widely applied to the reactor neutronics calculation. Conveying applianceThe neutron calculation of the system reactor generally utilizes a two-step approach to simplify the calculation: firstly, carrying out two-dimensional multi-group transport calculation on part of a core stack by utilizing a grid program under approximate boundary conditions, and replacing a fine inhomogeneous medium with an equivalent homogeneous medium through one or more times of homogenization treatment; and secondly, performing few groups of low-order transport calculation on the homogenized three-dimensional whole reactor core to obtain the power density distribution of the fuel rods required by safety analysis.
In the two-step calculation, a two-step calculation scheme taking an assembly homogenization theory and a coarse mesh block method as a theoretical framework is a traditional fuel management numerical calculation method commonly adopted in pressurized water reactor engineering calculation at present. With the continuous deepening of scientific research and the continuous improvement of computing conditions and requirements on the computing precision of nuclear design, the traditional two-step computing scheme faces more and more serious challenges. Firstly, the target result of the core nuclear design is the single-rod power density distribution in the three-dimensional full core, but in the traditional two-step method, all fuel rods (grid cells) in the assembly are considered uniformly through a homogenization technology, only the total nuclear reaction rate and the neutron leakage rate are guaranteed to be conserved, each fuel rod cannot be distinguished and treated, then after the full core coarse mesh block is calculated, the power density distribution of each fuel rod in the assembly is pieced together by adopting a fine power distribution reconstruction technology, and a large error is introduced. Secondly, with the continuous proposition of new nuclear reactor concept and the continuous innovation of reactor fuel and core design, the characteristics of the core of the new generation of pressurized water reactor, such as stronger heterogeneity, stronger neutron leakage, enhanced neutron spectrum interference effect between adjacent components due to the increase of fuel types, and the like, make the calculation precision of the traditional two-step method for homogenizing the components more and more unable to meet the requirement of engineering calculation precision, such as small pressurized water reactor and MOX-UO2Mixed loading, etc.
In order to improve the calculation precision of the reactor core design and meet the precision requirement of the calculation of the novel reactor core, the whole reactor core is calculated rod by rod to become a research hotspot of the next generation of reactor core numerical calculation method. The calculation scheme is characterized in that grid cell homogenization calculation is performed after single-component non-uniformity one-step calculation under the boundary condition of total reflection to obtain a grid cell homogenization constant for the reactor core, a grid cell homogenization fine net replaces a component homogenization coarse net, and the neutron calculation of the reactor core is performed by adopting an energy group structure and a low-order transport calculation method which are more than two groups.
However, as the spatial grid of the core calculation is changed from a coarse grid of component homogenization to a fine grid of cell homogenization, the homogenization region is also changed from a light-thick medium to a light-thin medium, and the core calculation becomes more precise and more complicated. The homogenization area is changed from light thickness to light thickness, so that the influences of environment effects such as neutron jet effect, neutron energy spectrum interference effect and the like brought by approximation of full-symmetry boundary conditions adopted in the non-uniform calculation process of the grids are increased, and the influences on different grid elements in the same grid are different. Therefore, how to research and design a cell uniformization constant calculation method, system and terminal considering environmental effect is a problem that needs to be solved urgently at present.
Disclosure of Invention
In order to solve the defects in the prior art, the invention aims to provide a cell homogenization constant calculation method, a system and a terminal considering the environmental effect, which can process the influence of the real reactor core environment on a homogenization section, which is not considered by the total reflection boundary condition in the cell homogenization constant calculation process, so as to improve the calculation accuracy of the cell homogenization constant.
The technical purpose of the invention is realized by the following technical scheme:
in a first aspect, a method for calculating a cell uniformization constant considering environmental effects is provided, which includes the following steps:
selecting the neutron characteristics of the reactor core according to the characteristic parameter conservation principle between the uniform reactor core calculation and the non-uniform grid calculation;
establishing a difference table of the discontinuity factor or the super homogenization factor and the neutron characteristic of the reactor core;
performing reactor core rod-by-rod calculation by using equivalent homogenization constants obtained by calculating single-component problems of various types under the condition of total reflection boundary to obtain reactor core neutronics characteristic quantity corresponding to reactor core neutronics characteristics in each grid cell;
and carrying out multi-dimensional linear interpolation processing on the neutron characteristic quantity in the reactor core according to the difference table, and accurately calculating to obtain the equivalent homogenization small group constant of the grid cells.
Furthermore, the neutron characteristics of the reactor core are selected from three neutron behavior modes of neutron leakage, neutron transfer and neutron generation.
Further, the neutron characteristics in the reactor core are divided into a first type characteristic quantity and a second type characteristic quantity;
the first type characteristic quantity is the non-variable quantity before and after the reactor core is homogenized, and the first type characteristic quantity is obtained by grid calculation of various fuel assemblies before the reactor core rod-by-rod calculation is carried out;
the second type of characteristic quantity is influenced by the calculation result of the reactor core rod by rod, and the second type of characteristic quantity is subjected to normalization calculation by taking the average neutron flux density as one.
Further, the first type characteristic quantity comprises center distance of the grid cells, uniform small group cross section and diffusion coefficient.
Further, the second type of characteristic quantity comprises neutron leakage rate and cell average reaction rate.
Further, the selection process of the neutron characteristics in the reactor core specifically comprises the following steps:
in the formula: x is the number ofiA vector representing the composition of the mathematical features in the ith cell core; di,gThe diffusion coefficient of the g-th energy group of the ith cell is expressed; sigmar,i,gShowing the removal cross section of the g-th energy group of the ith cell; si,gRepresenting the sum of fission sources and scattering sources of the g-th energy group of the ith cell;
representing the neutron flux density of the four surfaces of the g energy group of the ith cell;
mean of g-th energy group of i-th cellThe sub-flux density.
Further, the process of establishing the difference table specifically includes:
extracting adjacent problems of different component types according to the reactor core arrangement scheme to form a problem library comprising single components and 2 multiplied by 2 components;
and (3) carrying out grid calculation on the problems in the problem library by adopting a component program under the condition of total reflection boundary, generating one-to-one correspondence between the discontinuous factors or the super homogenization factors and the neutron characteristics in the reactor core, and integrating all the correspondence to obtain a difference table.
In a second aspect, there is provided a cell uniformization constant calculation system considering environmental effects, including:
the selection module is used for selecting the neutron characteristics of the reactor core according to the characteristic parameter conservation principle between the uniform reactor core calculation and the non-uniform grid calculation;
the construction module is used for establishing a difference table of the discontinuity factor or the super homogenization factor and the neutron characteristics in the reactor core;
the calculation module is used for performing reactor core rod-by-rod calculation by using equivalent homogenization constants obtained by calculation of single-component problems of various types under the boundary condition of total reflection to obtain reactor core neutron characteristic quantities corresponding to the reactor core neutron characteristics in the grid cells;
and the interpolation module is used for carrying out multi-dimensional linear interpolation processing on the neutron characteristic quantity in the reactor core according to the difference table and accurately calculating to obtain the equivalent homogenization small group constant of the grid cells.
Further, the building module comprises:
the extraction unit is used for extracting adjacent problems of different component types according to the reactor core arrangement scheme to form a problem library comprising single components and 2 multiplied by 2 components;
and the calculation integration unit is used for performing grid calculation on the problems in the problem library by adopting a component program under the condition of total reflection boundary, generating one-to-one correspondence between the discontinuous factors or the super homogenization factors and the neutron characteristics in the reactor core, and obtaining a difference table after integrating all the correspondence.
In a third aspect, a computer terminal is provided, which includes a memory, a processor, and a computer program stored in the memory and executable on the processor, and when the processor executes the program, the method for calculating a cell uniformization constant considering an environmental effect according to any one of the first aspect is implemented.
Compared with the prior art, the invention has the following beneficial effects:
the invention establishes a difference table of the cell homogenization constants and the neutron characteristic quantities based on the multi-dimensional linear interpolation technology, then accurately calculates the cell homogenization constants required by the actual reactor core rod-by-rod calculation according to the reactor core rod-by-rod calculation results, and effectively weakens the influence of the real reactor core environment not considered by the total reflection boundary conditions on the homogenization section in the calculation process of the cell homogenization constants, thereby improving the reactor core rod-by-rod calculation precision and providing an important support function for the calculation of the whole reactor core rod-by-rod into the next generation of mainstream reactor core numerical value.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
FIG. 1 is a flow chart in an embodiment of the invention;
fig. 2 is a block diagram of a system in an embodiment of the invention.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention will be further described in detail with reference to the following examples and accompanying fig. 1-2, wherein the exemplary embodiments and descriptions of the present invention are only used for explaining the present invention and are not used as limitations of the present invention.
Example 1: the method for calculating the cell uniformization constant by considering the environmental effect, as shown in fig. 1, comprises the following steps:
s1: selecting the neutron characteristics of the reactor core according to the characteristic parameter conservation principle between the uniform reactor core calculation and the non-uniform grid calculation;
s2: establishing a difference table of the discontinuity factor or the super homogenization factor and the neutron characteristic of the reactor core;
s3: performing reactor core rod-by-rod calculation by using equivalent homogenization constants obtained by calculating single-component problems of various types under the condition of total reflection boundary to obtain reactor core neutronics characteristic quantity corresponding to reactor core neutronics characteristics in each grid cell;
s4: and carrying out multi-dimensional linear interpolation processing on the neutron characteristic quantity in the reactor core according to the difference table, and accurately calculating to obtain the equivalent homogenization small group constant of the grid cells.
The cell homogenization constant is composed of various cell homogenization sections and discontinuous factors or super homogenization factors. In the cell homogenization theoretical model, the calculation of the homogenization cross section is solved by a flux volume weighting method. Compared with a homogenization section, the influence of environmental effects caused by the fact that the total reflection boundary conditions of the single component problem are different from the environments of the single component problem in the real reactor core on the discontinuous factors or the super homogenization factors is obvious, and therefore the capability that the calculation accuracy of the cell homogenization reactor core can be effectively improved by calculating the discontinuous factors or the super homogenization factors capable of considering the environmental effects is calculated.
Under the condition that the real boundary conditions of each component of the reactor core cannot be known in advance, the constant function prediction method enhances the identification degree of the grid element equivalent homogenization small group constant on the environmental effect based on a multi-dimensional linear interpolation method and reduces the calculation error of the reactor core rod by rod.
In step S1, the neutron characteristics of the core are selected based on neutron leakage, neutron transport, and neutron generation.
The neutron characteristic quantities related to the neutron behavior modes can be divided into a first type characteristic quantity and a second type characteristic quantity according to the three neutron behavior modes. The first type characteristic quantity is the non-variable quantity before and after the reactor core is homogenized, and the first type characteristic quantity is calculated by grids of various fuel assemblies before the reactor core rod-by-rod calculation. The second characteristic quantity is influenced by the reactor core rod-by-rod calculation result, and in order to avoid numerical calculation errors caused by overlarge value difference of each neutron characteristic in the multi-dimensional linear interpolation, the second characteristic quantity adopts the average neutron flux density as one to carry out normalization calculation.
The first type of characteristic quantity includes, but is not limited to, a cell center distance, a uniform small group cross section, and a diffusion coefficient. The second category of characteristic quantities includes, but is not limited to, neutron leak rate, cell average reactivity rate.
In this embodiment, the process of selecting the neutron characteristics in the reactor core specifically includes:
in the formula: x is the number ofiA vector representing the composition of the mathematical features in the ith cell core; di,gThe diffusion coefficient of the g-th energy group of the ith cell is expressed; sigmar,i,gShowing the removal cross section of the g-th energy group of the ith cell; si,gRepresenting the sum of fission sources and scattering sources of the g-th energy group of the ith cell;
representing the neutron flux density of the four surfaces of the g energy group of the ith cell;
represents the average neutron flux density of the ith cell gth energy group.
In step S2, the process of establishing the difference table specifically includes: extracting adjacent problems of different component types according to the reactor core arrangement scheme to form a problem library comprising single components and 2 multiplied by 2 components; and (3) carrying out grid calculation on the problems in the problem library by adopting a component program under the condition of total reflection boundary, generating one-to-one correspondence between the discontinuous factors or the super homogenization factors and the neutron characteristics in the reactor core, and integrating all the correspondence to obtain a difference table.
Example 2: the cell homogenization constant calculation system considering the environmental effect is used for implementing the method described in embodiment 1, and as shown in fig. 2, the system includes a selection module, a construction module, a calculation module, and an interpolation module.
The selection module is used for selecting the neutron characteristics in the reactor core according to the characteristic parameter conservation principle between the uniform reactor core calculation and the non-uniform grid calculation. And the construction module is used for establishing a difference table of the discontinuity factor or the super homogenization factor and the neutron characteristics in the reactor core. And the calculation module is used for performing reactor core rod-by-rod calculation by using the equivalent homogenization constant obtained by calculating each type of single-component problem under the boundary condition of total reflection to obtain the reactor core neutron characteristic quantity corresponding to the reactor core neutron characteristic in each grid cell. And the interpolation module is used for carrying out multi-dimensional linear interpolation processing on the neutron characteristic quantity in the reactor core according to the difference table and accurately calculating to obtain the equivalent homogenization small group constant of the grid cells.
The building module comprises an extraction unit and a calculation integration unit. The extraction unit is used for extracting adjacent problems of different component types according to the core arrangement scheme to form a problem library comprising single components and 2 x 2 components. And the calculation integration unit is used for performing grid calculation on the problems in the problem library by adopting a component program under the condition of total reflection boundary, generating one-to-one correspondence between the discontinuous factors or the super homogenization factors and the neutron characteristics in the reactor core, and obtaining a difference table after integrating all the correspondence.
The working principle is as follows: the invention establishes a difference table of the cell homogenization constants and the neutron characteristic quantities based on the multi-dimensional linear interpolation technology, then accurately calculates the cell homogenization constants required by the actual reactor core rod-by-rod calculation according to the reactor core rod-by-rod calculation results, and effectively weakens the influence of the real reactor core environment not considered by the total reflection boundary conditions on the homogenization section in the calculation process of the cell homogenization constants, thereby improving the reactor core rod-by-rod calculation precision and providing an important support function for the calculation of the whole reactor core rod-by-rod into the next generation of mainstream reactor core numerical value.
As will be appreciated by one skilled in the art, embodiments of the present application may be provided as a method, system, or computer program product. Accordingly, the present application may take the form of an entirely hardware embodiment, an entirely software embodiment or an embodiment combining software and hardware aspects. Furthermore, the present application may take the form of a computer program product embodied on one or more computer-usable storage media (including, but not limited to, disk storage, CD-ROM, optical storage, and the like) having computer-usable program code embodied therein.
The present application is described with reference to flowchart illustrations and/or block diagrams of methods, apparatus (systems), and computer program products according to embodiments of the application. It will be understood that each flow and/or block of the flow diagrams and/or block diagrams, and combinations of flows and/or blocks in the flow diagrams and/or block diagrams, can be implemented by computer program instructions. These computer program instructions may be provided to a processor of a general purpose computer, special purpose computer, embedded processor, or other programmable data processing apparatus to produce a machine, such that the instructions, which execute via the processor of the computer or other programmable data processing apparatus, create means for implementing the functions specified in the flowchart flow or flows and/or block diagram block or blocks.
These computer program instructions may also be stored in a computer-readable memory that can direct a computer or other programmable data processing apparatus to function in a particular manner, such that the instructions stored in the computer-readable memory produce an article of manufacture including instruction means which implement the function specified in the flowchart flow or flows and/or block diagram block or blocks.
These computer program instructions may also be loaded onto a computer or other programmable data processing apparatus to cause a series of operational steps to be performed on the computer or other programmable apparatus to produce a computer implemented process such that the instructions which execute on the computer or other programmable apparatus provide steps for implementing the functions specified in the flowchart flow or flows and/or block diagram block or blocks.
The above embodiments are provided to further explain the objects, technical solutions and advantages of the present invention in detail, it should be understood that the above embodiments are merely exemplary embodiments of the present invention and are not intended to limit the scope of the present invention, and any modifications, equivalents, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (7)
1. The method for calculating the cell homogenization constant considering the environmental effect is characterized by comprising the following steps of:
selecting the neutron characteristics of the reactor core according to the characteristic parameter conservation principle between the uniform reactor core calculation and the non-uniform grid calculation;
establishing a difference table of the discontinuity factor or the super homogenization factor and the neutron characteristic of the reactor core;
performing reactor core rod-by-rod calculation by using equivalent homogenization constants obtained by calculating single-component problems of various types under the condition of total reflection boundary to obtain reactor core neutronics characteristic quantity corresponding to reactor core neutronics characteristics in each grid cell;
performing multi-dimensional linear interpolation processing on the neutron characteristic quantity in the reactor core according to the difference table, and accurately calculating to obtain a grid cell equivalent homogenization small group constant;
the neutron characteristics of the reactor core are selected from three neutron behavior modes of neutron leakage, neutron transfer and neutron generation;
the selection process of the neutron characteristics in the reactor core specifically comprises the following steps:
in the formula: x is the number ofiA vector representing the composition of the mathematical features in the ith cell core; di,gThe diffusion coefficient of the g-th energy group of the ith cell is expressed; sigmar,i,gShowing the removal cross section of the g-th energy group of the ith cell; si,gRepresenting the sum of fission sources and scattering sources of the g-th energy group of the ith cell;
representing the neutron flux density of the four surfaces of the g energy group of the ith cell;
representing the average neutron flux density of the g energy group of the ith cell;
the establishing process of the difference table specifically comprises the following steps:
extracting adjacent problems of different component types according to the reactor core arrangement scheme to form a problem library comprising single components and 2 multiplied by 2 components;
and (3) carrying out grid calculation on the problems in the problem library by adopting a component program under the condition of total reflection boundary, generating one-to-one correspondence between the discontinuous factors or the super homogenization factors and the neutron characteristics in the reactor core, and integrating all the correspondence to obtain a difference table.
2. The method of calculating a cell homogenization constant considering environmental effects of claim 1, wherein the neutron characteristics in the core are classified into a first type characteristic quantity and a second type characteristic quantity;
the first type characteristic quantity is the non-variable quantity before and after the reactor core is homogenized, and the first type characteristic quantity is obtained by grid calculation of various fuel assemblies before the reactor core rod-by-rod calculation is carried out;
the second type of characteristic quantity is influenced by the calculation result of the reactor core rod by rod, and the second type of characteristic quantity is subjected to normalization calculation by taking the average neutron flux density as one.
3. The method of calculating cell uniformity constants taking into account environmental effects of claim 2, wherein said first type of characteristic quantities include cell center-to-center distance, uniformity low population cross-section, and diffusion coefficient.
4. The method of calculating a cell homogenization constant considering environmental effects as claimed in claim 2, wherein the second type of characteristic quantity includes a neutron leak rate, a cell average response rate.
5. A cell uniformization constant calculation system considering environmental effects is characterized by comprising:
the selection module is used for selecting the neutron characteristics of the reactor core according to the characteristic parameter conservation principle between the uniform reactor core calculation and the non-uniform grid calculation;
the construction module is used for establishing a difference table of the discontinuity factor or the super homogenization factor and the neutron characteristics in the reactor core;
the calculation module is used for performing reactor core rod-by-rod calculation by using equivalent homogenization constants obtained by calculation of single-component problems of various types under the boundary condition of total reflection to obtain reactor core neutron characteristic quantities corresponding to the reactor core neutron characteristics in the grid cells;
the interpolation module is used for carrying out multi-dimensional linear interpolation processing on the neutron characteristic quantity in the reactor core according to the difference table and accurately calculating to obtain the equivalent homogenization small group constant of the grid cell;
the neutron characteristics of the reactor core are selected from three neutron behavior modes of neutron leakage, neutron transfer and neutron generation;
the selection process of the neutron characteristics in the reactor core specifically comprises the following steps:
in the formula: x is the number ofiA vector representing the composition of the mathematical features in the ith cell core; di,gThe diffusion coefficient of the g-th energy group of the ith cell is expressed; sigmar,i,gShowing the removal cross section of the g-th energy group of the ith cell; si,gRepresenting the sum of fission sources and scattering sources of the g-th energy group of the ith cell;
representing the neutron flux density of the four surfaces of the g energy group of the ith cell;
representing the average neutron flux density of the g energy group of the ith cell;
the establishing process of the difference table specifically comprises the following steps:
extracting adjacent problems of different component types according to the reactor core arrangement scheme to form a problem library comprising single components and 2 multiplied by 2 components;
and (3) carrying out grid calculation on the problems in the problem library by adopting a component program under the condition of total reflection boundary, generating one-to-one correspondence between the discontinuous factors or the super homogenization factors and the neutron characteristics in the reactor core, and integrating all the correspondence to obtain a difference table.
6. The system of claim 5, wherein the building block comprises:
the extraction unit is used for extracting adjacent problems of different component types according to the reactor core arrangement scheme to form a problem library comprising single components and 2 multiplied by 2 components;
and the calculation integration unit is used for performing grid calculation on the problems in the problem library by adopting a component program under the condition of total reflection boundary, generating one-to-one correspondence between the discontinuous factors or the super homogenization factors and the neutron characteristics in the reactor core, and obtaining a difference table after integrating all the correspondence.
7. A computer terminal comprising a memory, a processor and a computer program stored in the memory and executable on the processor, wherein the processor implements the method for cell uniformity constant calculation considering environmental effects as claimed in any one of claims 1 to 4 when executing the program.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110671019.9A CN113326648B (en) | 2021-06-17 | 2021-06-17 | Cell homogenization constant calculation method and system considering environmental effect and terminal |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110671019.9A CN113326648B (en) | 2021-06-17 | 2021-06-17 | Cell homogenization constant calculation method and system considering environmental effect and terminal |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN113326648A CN113326648A (en) | 2021-08-31 |
| CN113326648B true CN113326648B (en) | 2022-02-22 |
Family
ID=77423598
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202110671019.9A Active CN113326648B (en) | 2021-06-17 | 2021-06-17 | Cell homogenization constant calculation method and system considering environmental effect and terminal |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN113326648B (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114840988B (en) * | 2022-04-22 | 2024-02-23 | 西安交通大学 | Automatic modeling method for pressurized water reactor core |
Family Cites Families (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103898363A (en) * | 2012-12-27 | 2014-07-02 | 中国核动力研究设计院 | Zirconium alloy for nuclear power |
| CN105303046B (en) * | 2015-10-30 | 2017-03-29 | 西安交通大学 | A kind of method for reducing reactor by component periphery rod power error in rod calculating |
| CN105808503B (en) * | 2016-03-07 | 2018-05-18 | 西安交通大学 | The method of Analytical Solution lattice cell discontinuous factor in being calculated for reactor by stick |
| CN106096182B (en) * | 2016-06-24 | 2019-04-09 | 西安交通大学 | A kind of reactor embedded resonance self-screen calculation method |
| CN106128518A (en) * | 2016-06-24 | 2016-11-16 | 西安交通大学 | A kind of method obtaining the few group cross-section of high-precision fast neutron reaction pile component |
| CN107092781B (en) * | 2017-04-05 | 2020-03-24 | 西安交通大学 | Calculation method for obtaining nuclear reactor high-fidelity resonance group constant |
| CN107103189B (en) * | 2017-04-13 | 2019-08-09 | 西安交通大学 | A Method for Searching Critical Curvature of Reactor |
| CN107423542B (en) * | 2017-04-13 | 2020-01-17 | 西安交通大学 | A non-uniform leakage correction method suitable for rod-by-rod calculation |
| CN107153732B (en) * | 2017-05-02 | 2020-08-04 | 西安交通大学 | A Pin-by-Pin method for analyzing the transient state of pressurized water reactor core |
| WO2019148420A1 (en) * | 2018-02-01 | 2019-08-08 | 国家电投集团科学技术研究院有限公司 | Reactor three-dimensional assembly information tracking method and system |
| CN110826205B (en) * | 2019-10-28 | 2021-08-13 | 西安交通大学 | An Energy Group Structure Optimization Method for Pin-by-pin Calculation of Pressurized Water Reactors |
| CN112347645B (en) * | 2020-11-06 | 2022-03-22 | 中国核动力研究设计院 | Method and device for reconstructing burnup characteristics of reactor core grid cells |
| CN112906272B (en) * | 2021-02-22 | 2022-04-15 | 中国核动力研究设计院 | Reactor steady-state physical thermal full-coupling fine numerical simulation method and system |
| CN112966428B (en) * | 2021-03-31 | 2022-08-05 | 清华大学 | Cross-section treatment system for reactor core |
-
2021
- 2021-06-17 CN CN202110671019.9A patent/CN113326648B/en active Active
Also Published As
| Publication number | Publication date |
|---|---|
| CN113326648A (en) | 2021-08-31 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| She et al. | PANGU code for pebble-bed HTGR reactor physics and fuel cycle simulations | |
| Khoshahval et al. | A new hybrid method for multi-objective fuel management optimization using parallel PSO-SA | |
| Park et al. | Practical resolution of angle dependency of multigroup resonance cross sections using parametrized spectral superhomogenization factors | |
| Bostelmann et al. | SCALE Analysis of a Fluoride Salt-Cooled High-Temperature Reactor in Support of Severe Accident Analysis | |
| Mao et al. | A new Tone's method in APOLLO3® and its application to fast and thermal reactor calculations | |
| CN113536580B (en) | Method and system for determining nuclear reactor test loop power and neutron flux density | |
| CN113326648B (en) | Cell homogenization constant calculation method and system considering environmental effect and terminal | |
| Wu et al. | Development and verification of a Monte Carlo two-step method for lead-based fast reactor neutronics analysis | |
| KR20010038820A (en) | Advanced Excore Detector Calibration Method | |
| Choi et al. | A New Equivalence Theory Method for Treating Doubly Heterogeneous Fuel—II: Verifications | |
| Rogers et al. | Optimization of PWR fuel assembly radial enrichment and burnable poison location based on adaptive simulated annealing | |
| Robert et al. | Evaluation of Serpent capabilities for hyperfidelity depletion of pebble bed cores | |
| Ade et al. | Development of MPACT for full-core simulations of MAGNOX gas-cooled nuclear reactors | |
| Yamamoto et al. | AEGIS: an advanced lattice physics code for light water reactor analyses | |
| CN114239437A (en) | Time step acceleration method for refining transient neutron transport calculation | |
| Hursin et al. | Monte Carlo analysis of BWR geometries using a cycle check-up methodology | |
| CN117371252A (en) | Multi-cycle fuel management fuel consumption tracking calculation method, system and medium | |
| CN113312792B (en) | Method and system for calculating equivalent homogenization constant of grid element in reactor core rod-by-rod calculation | |
| Batki et al. | Extension and application of the KIKO3DMG nodal code for fast reactor core analyses | |
| CN116682585A (en) | Analysis method, device and equipment for uncertainty of reactor core power distribution measurement | |
| CN119227404B (en) | A fast fuel management model for liquid metal fast reactors and its construction method and application | |
| Wu et al. | Development of a design method for burnable poisons in small modular fast reactors | |
| CN117524325B (en) | Method and device for calculating transient spliced fission matrix of reactor core model | |
| Jeong et al. | Verification of DeCART2D/CAPP code system for VHTR analysis with PMR-200 benchmark | |
| Krepel et al. | Mapping of sodium void effect and Doppler constant in ESFR-SMART core with Monte Carlo code serpent and deterministic code Eranos |
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 | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |