Compatibility calculation method of full core and quarter core in fuel management program

Abstract

The present invention discloses a method for calculating and processing compatibility of a full core and a quarter core in a fuel management program, and relates to the technical field of nuclear reactor cores. The key points of the technical solution are: the spatial size of variables storing geometric information in a quarter core and the value of the variables are redistributed and calculated according to the geometric information of the full core; the node coordinates of the quarter core calculation area are converted into coordinates in the full core, and the variables related to the faces of each node in the quarter core calculation area are assigned according to the component rotation method used in the full core calculation; when the core refueling calculation is performed in the quarter core calculation area, the component information of the quadrant corresponding to the current cycle quarter core calculation area is exchanged according to the information in the upstream quarter core library for processing. The present invention adopts the same program architecture and the same set of data structures in the existing fuel management program to realize the neutronics compatibility calculation of the full core and the 1 / 4 core.

Description

Technical Field

[0001] The present invention relates to the technical field of nuclear reactor cores, and more particularly to a method for calculating and processing compatibility of a full core and a quarter core in a fuel management program. Background Art

[0002] The core fuel management program is mainly used for the selection of core refueling schemes, as well as nuclear calculation and safety evaluation of refueling cores. It is usually composed of a component program and a core calculation program to form a "two-step" fuel management program package, such as KYLIN-II / CORCA-3D of China Nuclear Power Research and Design Institute.

[0003] At present, the component programs in the fuel management package usually use a quarter component as the calculation unit, and the calculation parameters are expanded to the whole component in a symmetrical manner, and then the core calculation is performed; the core calculation radially uses a single component or a quarter component as the calculation grid, and the total number of grids is usually in the tens of thousands, which is not particularly large, so the full core calculation mode is usually used directly. The core calculation of fuel management has many calculation functions such as core loading, refueling and fuel consumption. The fuel management process requires designers to repeatedly calculate whether the design loading meets the safety standards and operation requirements. When the design criteria are met, key parameters such as the core hot spot factor will be adjusted to the optimal level as much as possible. The whole process requires a large number of core calculations, so the calculation amount is considerable and it will occupy a large storage space.

[0004] In order to improve the work efficiency and calculation needs of designers, considering that the core loading is usually one-quarter rotational symmetry or mirror symmetry, 1 / 4 symmetric core calculation is specially studied. In order to meet the full core and 1 / 4 core calculations at the same time, and take into account the ease of use of the fuel management package and the simplicity and readability of the code, the core neutronics software needs to be designed in the calculation process, the automatic conversion of the data structure of the full core and the partial core, so it is necessary to design this full core and 1 / 4 automatic switching calculation technology. Summary of the invention

[0005] To address the deficiencies in the prior art, the purpose of the present invention is to provide a method for compatible calculation and processing of the full core and a quarter core in a fuel management program. In the existing fuel management program, the same program architecture and the same set of data structures are used in geometric coordinate processing, node and surface information processing, and material change calculation, respectively, to concisely and effectively implement neutronics compatible calculations of the full core and 1 / 4 core, providing users with tools for multi-form calculations.

[0006] The above technical objectives of the present invention are achieved through the following technical solutions:

[0007] In a first aspect, a method for calculating and processing compatibility of a full core and a quarter core in a fuel management program is provided, comprising the following steps:

[0008] According to the geometric information of the whole core, the space size of the variables storing the geometric information and the values ​​of the variables in the quarter core are reallocated and calculated;

[0009] The node coordinates of the quarter core calculation area are converted into the coordinates in the full core, and the variables related to the surface of each node in the quarter core calculation area are assigned values ​​according to the component rotation method used in the full core calculation;

[0010] When the core refueling calculation is performed in the quarter core calculation area, the component information of the quadrant corresponding to the quarter core calculation area of ​​the current cycle is processed according to the information in the upstream quarter core library.

[0011] Furthermore, the variables include component coordinates, component numbers, component numbers, node coordinates, fuel zone numbers, control rod coordinates, control rod numbers, node side lengths, and node volumes.

[0012] Furthermore, the calculation formula for the number of components and nodes of the quarter core is specifically:

[0013]

[0014] Among them, ua0 and va0 are the number of components of the whole core in the U and V directions respectively; ua and va are the number of components of a quarter of the core in the U and V directions respectively; un0 and vn0 are the number of nodes of the whole core in the U and V directions respectively; un and vn are the number of nodes of a quarter of the core in the U and V directions respectively; / is the integer division operator; % is the modulus operator.

[0015] Furthermore, the calculation formulas for the component coordinates and node coordinates of the quarter core are specifically as follows:

[0016]

[0017] Among them, the component coordinates of the components in the full core and a quarter of the core are (xa, ya) and (xa4, ya4) respectively, and the nodal coordinates of the nodes in the full core and a quarter of the core are (xn, yn) and (xn4, yn4) respectively.

[0018] Furthermore, if the horizontal coordinate and the vertical coordinate in the component coordinate corresponding to the component in the quarter core are both greater than 0, then the component is in the quarter core calculation area;

[0019] If the abscissa and ordinate of the node coordinates corresponding to the node in the quarter core are both greater than 0, the node is in the quarter core calculation area.

[0020] Furthermore, the calculation formula for converting the node coordinates of the quarter core calculation area into the coordinates in the full core is specifically:

[0021] xn'=xn4+un0 / 2

[0022] yn'=yn4+vn0 / 2

[0023] Among them, (xn4,yn4) is the coordinate of the node in one quarter of the core; (xn',yn') is the coordinate of the node in one quarter of the core in the whole core; / is the integer division operator; un0 and vn0 are the number of nodes in the whole core in the U and V directions respectively.

[0024] Furthermore, the process of assigning values ​​to variables related to each node and surface in the quarter core calculation area according to the component rotation mode used in the full core calculation is specifically as follows:

[0025] Determine the area of ​​the node in the component;

[0026] The node is rotated clockwise by 90°, 180°, and 270° to the third area, the first area, and the second area of ​​the component, respectively, with the symbol f i,j Represents the discontinuity factor of face j of node i, and determines the relationship between the discontinuity factor of each face of each node and the face of the node calculated by the component.

[0027] Furthermore, when the core refueling calculation is performed in the quarter core calculation area, for the refueling situation of replacing the historical cycle components in the fourth quadrant to the fourth quadrant of the current cycle, the burnup depth, surface burnup and nuclear density of the historical cycle components can be directly obtained by reading the upstream quarter core library of the current calculation.

[0028] Furthermore, when the core refueling calculation is performed in the quarter core calculation area, for the refueling situation of replacing the historical cycle components in the first quadrant, the second quadrant, and the third quadrant to the fourth quadrant of the current cycle, the relevant information of the historical cycle components needs to be expanded from the information in the upstream quarter core library according to the symmetry of the core.

[0029] Furthermore, when the core refueling calculation is performed in the quarter core calculation area, if the central component is not a new component but an old non-central component of the historical cycle, the burnup depth and nuclear density of the central component are the average values ​​of the corresponding values ​​of all nodes in the component, and the surface burnup value of the central node is the average value obtained after rotational symmetry of all nodes in the component.

[0030] Compared with the prior art, the present invention has the following beneficial effects:

[0031] The present invention provides a method for processing compatible calculations of the full core and a quarter core in a fuel management program. In the existing fuel management program, the same program architecture and the same set of data structures are used in geometric coordinate processing, node and surface information processing, and material change calculation, respectively, to concisely and effectively implement neutronics compatible calculations of the full core and a quarter core, providing a tool for users to perform multi-form calculations. BRIEF DESCRIPTION OF THE DRAWINGS

[0032] The drawings described herein are used to provide a further understanding of the embodiments of the present invention, constitute a part of this application, and do not constitute a limitation of the embodiments of the present invention. In the drawings:

[0033] Figure 1 1 is a schematic diagram of coordinates of a full core and a quarter of a calculated core in an embodiment of the present invention;

[0034] Figure 2 Schematic diagram of the relationship between the side lengths of a full core and a quarter core segment in an embodiment of the present invention;

[0035] Figure 3 is a schematic diagram of the numbering of component areas divided into 2×2 in an embodiment of the present invention;

[0036] Figure 4 is a schematic diagram of the relationship between the node surfaces of each region of the rotationally symmetric component in an embodiment of the present invention;

[0037] Figure 5 1 is a schematic diagram of the numbering of quadrants of the entire core in an embodiment of the present invention;

[0038] Figure 6 Schematic diagram of the numbering of each block surface in an embodiment of the present invention;

[0039] Figure 7 It is a schematic diagram of the relationship between the rotation of one quarter of the central component to each segment surface in an embodiment of the present invention. DETAILED DESCRIPTION

[0040] In order to make the objectives, technical solutions and advantages of the present invention more clearly understood, the present invention is further described in detail below in conjunction with embodiments and drawings. The exemplary embodiments of the present invention and their description are only used to explain the present invention and are not intended to limit the present invention.

[0041] It should be noted that when a component is referred to as being "fixed to" or "disposed on" another component, it can be directly on the other component or indirectly on the other component. When a component is referred to as being "connected to" another component, it can be directly or indirectly connected to the other component.

[0042] It should be understood that the orientation or position relationship indicated by terms such as "length", "width", "up", "down", "front", "back", "left", "right", "vertical", "horizontal", "top", "bottom", "inside" and "outside" are based on the orientation or position relationship shown in the drawings, and are only for the convenience of describing the present invention and simplifying the description, and do not indicate or imply that the device or element referred to must have a specific orientation, be constructed and operate in a specific orientation, and therefore cannot be understood as a limitation on the present invention.

[0043] In addition, the terms "first" and "second" are used for descriptive purposes only and should not be understood as indicating or implying relative importance or implicitly indicating the number of the indicated technical features. Therefore, the features defined as "first" and "second" may explicitly or implicitly include one or more of the features. In the description of the present invention, the meaning of "plurality" is two or more, unless otherwise clearly and specifically defined.

[0044] Example

[0045] At present, the core layout of nuclear power plants adopts the quarter rotational symmetry method, and the single side is an odd number of components. Therefore, the design process defaults to 1 / 4 rotational symmetry and a single side odd number of components. Core loading and refueling are the two core functional modules in fuel management. For these two engineering modules, the design process of full core and 1 / 4 core automatic switching calculation is introduced in detail, and the processing method is introduced in detail from the aspects of geometric coordinates, node surface information and parameter assignment in refueling calculation.

[0046] The full core and quarter core compatibility calculation processing method in the fuel management program includes the following steps:

[0047] S1: reallocate and calculate the space size and value of the variables storing the geometric information in the quarter core according to the geometric information of the whole core;

[0048] S2: Convert the node coordinates in the quarter core calculation area into the coordinates in the full core, and assign values ​​to the variables related to the surface of each node in the quarter core calculation area according to the component rotation method used in the full core calculation;

[0049] S3: When performing core refueling calculation in the quarter core calculation area, the component information of the quadrant corresponding to the quarter core calculation area of ​​the current cycle is processed according to the information in the upstream quarter core library.

[0050] In step S1, the core calculation adopts the coarse-grid node method, which usually divides a component into a calculation node or 2×2 nodes as a calculation unit. Figure 1 As shown, the quarter core calculation selects the lower right quarter of the full core for calculation, see Figure 1 The red line encloses the area in the middle, so the space size of the variables storing geometric information in one quarter of the core. The values ​​of the variables need to be redistributed and calculated, mainly including the core component coordinates, component number, number of components, block coordinates, fuel zone number, control rod coordinates, number of control rods, node side length, node volume and other variables.

[0051] exist Figure 1 REF(u,v): The coordinates of the reflector assembly node in the whole core are (u,v). Fn(u,v): The fuel assembly node in the whole core is numbered n in the whole core and has coordinates (u,v). The fuel assembly node in one quarter of the core is labeled m and has coordinates (j, k). The coordinates of the reflector assembly node in one quarter of the core are (j, k).

[0052] The calculation formula for the number of components and nodes of a quarter core is as follows:

[0053]

[0054] Among them, ua0 and va0 are the number of components of the whole core in the U and V directions respectively; ua and va are the number of components of a quarter of the core in the U and V directions respectively; un0 and vn0 are the number of nodes of the whole core in the U and V directions respectively; un and vn are the number of nodes of a quarter of the core in the U and V directions respectively; / is the integer division operator; % is the modulus operator.

[0055] The calculation formulas for the component coordinates and node coordinates of a quarter of the core are as follows:

[0056]

[0057] Among them, the component coordinates of the components in the full core and a quarter of the core are (xa, ya) and (xa4, ya4) respectively, and the nodal coordinates of the nodes in the full core and a quarter of the core are (xn, yn) and (xn4, yn4) respectively.

[0058] It should be noted that the component is in the quarter core calculation area only when xa4 and ya4 are both greater than 0. Similarly, the node is in the quarter core calculation area and is a valid calculation node only when xn4 and yn4 are both greater than 0.

[0059] When the number of nodes in the U and V directions of the whole core is an even number, the length of all nodes in the U and V directions of the quarter core is consistent with the length of the nodes in the U and V directions of the whole core. When the number of nodes in the U and V directions of the whole core is an odd number, the length of the nodes in the first row and the first column of the quarter core is not consistent with the length of other nodes in the core. For example, in a 5×5 core with only one node in each assembly, Figure 2 As shown, the length of all nodes in the first column of a quarter core in the U direction (AB) and the length of all nodes in the first row in the V direction (AC) are half of the length of the nodes in the U and V directions (DE, DF) of the full core.

[0060] In step S2, in the full core calculation mode, the nodes are directly assigned according to the component rotation mode, but in the quarter calculation mode, the component is radially divided into 2×2 nodes, and the number of nodes in the radial U and V directions is an odd number, the assignment of the face-related variables of the nodes in the first row and the first column of the quarter core needs to be processed, such as the face discontinuity factor. This variable is an important parameter in the small group parameter library of the component. The node coordinates of the quarter core calculation area need to be temporarily converted into coordinates in the full core, the area of ​​the node in the component is determined, and then the face-related variables of each node are assigned according to the component rotation mode. The area numbering in the core calculation program is from left to right and then from top to bottom to number the area where each node in the component is located. Figure 3 The following is a schematic diagram of the area numbering of each node in the 2×2 partition component. Figure 1 As shown, the first row of the block f 1 In area 4 of the component, In area 3 of the component, In area 4 of the component, In area 2 of the component to which it belongs, the assignment of face-related variables in these nodes needs to be processed in the following three steps.

[0061] Step 1: Process the coordinates of the nodes in 1 / 4 of the core.

[0062] Temporarily convert the node coordinates of the 1 / 4 core calculation area into coordinates in the whole core to prepare for the second step;

[0063] xn'=xn4+un0 / 2

[0064] yn'=yn4+vn0 / 2

[0065] Among them, (xn4,yn4) is the coordinate of the node in one quarter of the core; (xn',yn') is the coordinate of the node in one quarter of the core in the whole core; / is the integer division operator; un0 and vn0 are the number of nodes in the whole core in the U and V directions respectively.

[0066] Step 2: Determine the area of ​​the node in the component.

[0067]

[0068] Step 3: Assign values ​​to variables related to each node and face according to the component rotation method.

[0069] like Figure 4 As shown, Figure 4 (a) is the node block of the component calculation, that is, the fourth area. The fourth area is rotated clockwise by 90°, 180°, and 270°, that is, Figure 4 (b) Figure 4 (c) Figure 4 (d) shows that the components are rotated to the third, first, and second regions respectively. The corresponding faces and numbers of each section are shown in Figure 4 The discontinuity factor of the node i face j is represented by the symbol f i,j It means that the relationship between the discontinuity factor of each face of each node and the face of the node calculated by the component is as follows:

[0070] a) First area:

[0071] b) Second area:

[0072] c) Third Region:

[0073] In step S3, in the core calculation program quarter calculation mode, when performing core refueling calculation, only the component information that is switched to the fourth quadrant of the current cycle is processed. The quadrant numbers of the entire core are as follows: Figure 5 As shown. For the refueling situation of replacing the historical cycle components in the fourth quadrant to the fourth quadrant of the current cycle, the burnup depth, surface burnup, nuclear density and other information of the historical cycle components can be directly obtained by reading the upstream quarter core library of the current calculation; for the refueling situation of replacing the historical cycle components in the first, second and third quadrants to the fourth quadrant of the current cycle, the relevant information of the historical cycle components needs to be expanded from the information in the upstream quarter core library according to the symmetry of the core.

[0074] When the central component is not a new component but a non-central old component from the historical cycle, the central component needs to be specially processed. The burnup depth and nucleon density of the central component are the average values ​​of the corresponding values ​​of all nodes in the component, and the surface burnup value of the central node is the average value obtained after the rotational symmetry of all nodes in the component. For example, in the quarter calculation mode, the component is radially divided into 2×2 nodes, and the number of nodes in the radial U and V directions is an odd number. Figure 6As shown in the figure, it is a schematic diagram of the numbering of the segment surface. When the original component is rotationally symmetrical, the corresponding situation of the surface when the quarter center component is rotated to the other three segments is shown in Figure 7 As shown, the surface burnup of each surface of block 4 (quarter center component) is calculated as follows, where the surface burnup value of block i surface j is represented by the symbol Sbu i,j express:

[0075] S 4,1 =(Sbu 1,3 +Sbu 2,2 +Sbu 3,4 +Sbu 4,1 ) / 4

[0076] S 4,2 =(Sbu 1,4 +Sbu 2,3 +Sbu 3,1 +Sbu 4,2 ) / 4

[0077] S 4,3 =(Sbu 1,1 +Sbu 2,4 +Sbu 3,2 +Sbu 4,3 ) / 4

[0078] S 4,4 =(Sbu 1,2 +Sbu 2,1 +Sbu 3,3 +Sbu 4,4 ) / 4.

[0079] Working principle: In the existing fuel management program, the present invention adopts the same program architecture and the same set of data structures in geometric coordinate processing, node and surface information processing, and material replacement calculation, so as to realize the neutronics compatible calculation of the whole core and 1 / 4 core in a concise and effective manner, and provide users with tools for multi-form calculations.

[0080] The specific implementation methods described above further illustrate the objectives, technical solutions and beneficial effects of the present invention in detail. It should be understood that the above description is only a specific implementation method of the present invention and is not intended to limit the scope of protection of the present invention. Any modifications, equivalent substitutions, improvements, etc. made within the spirit and principles of the present invention should be included in the scope of protection of the present invention.

Claims

1. A method for calculating and processing the compatibility of the full core and the quarter core in the fuel management program, characterized in that: The following steps are involved: According to the geometric information of the whole core, the space size of the variables storing the geometric information and the values ​​of the variables in the quarter core are reallocated and calculated; The node coordinates of the quarter core calculation area are converted into the coordinates in the full core, and the variables related to the surface of each node in the quarter core calculation area are assigned values ​​according to the component rotation method used in the full core calculation; When performing core refueling calculation in the quarter core calculation area, the component information of the quadrant corresponding to the quarter core calculation area of ​​the current cycle is processed according to the information in the upstream quarter core library; The specific calculation formula for the number of components and nodes of the quarter core is: Among them, ua0 and va0 are the number of components of the whole core in the U and V directions respectively; ua and va are the number of components of a quarter of the core in the U and V directions respectively; un0 and vn0 are the number of nodes of the whole core in the U and V directions respectively; un and vn are the number of nodes of a quarter of the core in the U and V directions respectively; / is the integer division operator; % is the modulus operator; The calculation formulas for the component coordinates and node coordinates of the quarter core are as follows: Among them, the component coordinates of the components in the full core and the quarter core are (xa, ya) and (xa4, ya4) respectively, and the node coordinates of the nodes in the full core and the quarter core are (xn, yn) and (xn4, yn4) respectively; The calculation formula for converting the node coordinates of the quarter core calculation area into the coordinates in the full core is specifically: xn'=xn4+un0 / 2 yn'=yn4+vn0 / 2 Among them, (xn4,yn4) is the coordinate of the node in one quarter of the core; (xn',yn') is the coordinate of the node in one quarter of the core in the whole core; / is the integer division operator; un0 and vn0 are the number of nodes in the whole core in the U and V directions respectively.

2. The method for calculating and processing the compatibility of the full core and the quarter core in the fuel management program according to claim 1, characterized in that: The variables include assembly coordinates, assembly numbers, number of assemblies, node coordinates, number of fuel zones, control rod coordinates, number of control rods, side length of nodes, and volume of nodes.

3. The method for calculating and processing the compatibility of the full core and the quarter core in the fuel management program according to claim 1, characterized in that: If the horizontal and vertical coordinates of the component coordinates corresponding to the component in the quarter core are both greater than 0, then the component is in the quarter core calculation area; If the abscissa and ordinate of the node coordinates corresponding to the node in the quarter core are both greater than 0, the node is in the quarter core calculation area.

4. The method for calculating and processing the compatibility of the full core and the quarter core in the fuel management program according to claim 1, characterized in that: The process of assigning values ​​to variables related to each node and surface in the quarter core calculation area according to the component rotation method used in the full core calculation is specifically as follows: Determine the area of ​​the node in the component; The node is rotated clockwise by 90°, 180°, and 270° to the third area, the first area, and the second area of ​​the component, respectively, with the symbol f i,j Represents the discontinuity factor of face j of node i, and determines the relationship between the discontinuity factor of each face of each node and the face of the node calculated by the component.

5. The method for calculating and processing the compatibility of the full core and the quarter core in the fuel management program according to claim 1, characterized in that: When the core refueling calculation is performed in the quarter core calculation area, for the refueling situation of replacing the historical cycle components in the fourth quadrant to the fourth quadrant of the current cycle, the burnup depth, surface burnup and nuclear density of the historical cycle components are obtained by reading the upstream quarter core library of the current calculation.

6. The method for calculating and processing the compatibility of the full core and the quarter core in the fuel management program according to claim 1, characterized in that: When performing core refueling calculation in the quarter core calculation area, for the refueling situation of replacing historical cycle components in the first quadrant, the second quadrant, and the third quadrant to the fourth quadrant of the current cycle, the relevant information of the historical cycle components is obtained by expanding the information in the upstream quarter core library based on the symmetry of the core.

7. The method for calculating and processing the compatibility of the full core and the quarter core in the fuel management program according to claim 1, characterized in that: When performing the core refueling calculation in the quarter core calculation area, if the central component is not a new component but a non-central old component of the historical cycle, the burnup depth and nuclear density of the central component are the average values ​​of the corresponding values ​​of all nodes in the component, and the surface burnup value of the central node is the average value obtained after rotational symmetry of all nodes in the component.

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