CN112364555A - Dual-heterogeneity space self-screening effect correction method, device, equipment and medium - Google Patents
Dual-heterogeneity space self-screening effect correction method, device, equipment and medium Download PDFInfo
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Abstract
The invention discloses a dual-heterogeneity space self-shielding effect correction method, a device, equipment and a medium, wherein the method calculates all neutron numbers escaping from a fuel surface and neutron numbers entering adjacent fuel grid cells to collide without any collision in a moderator after escaping from the fuel surface by a Monte Carlo method to obtain a Danconf factor, and then corrects neutron escaping probability by the Danconf factor to correct dual heterogeneity calculated by neutron resonance; according to the fact that the escape probability of neutrons before and after the neutrons are uniform in the random distribution medium area is unchanged, the random distribution medium area is equivalent to a uniform medium; and calculating the equivalent section of the homogenized medium based on the macroscopic sections of the dispersion particles and each sub-area of the matrix, and the corresponding volume fraction and the space self-shielding factor of each sub-area to correct the dual heterogeneity of the neutron transport calculation, realize the correction of the dual heterogeneity space self-shielding effect of the randomly distributed medium fuel element, and improve the neutron calculation accuracy.
Description
Technical Field
The invention relates to the technical field of nuclear reactor cores, in particular to a method, a device, equipment and a medium for correcting a dual-heterogeneity space self-shielding effect.
Background
The safety of nuclear fuels under accident conditions is more and more emphasized, and in order to improve the safety of nuclear reactors, a design of dispersing fuel particles in a non-fissile matrix material, called as a randomly distributed medium fuel element, appears. From the neutron calculation point of view, the key difference between the random distribution medium fuel element and the traditional fuel element is that the fuel particles are dispersed in the matrix in the form of the random distribution medium, and a definite geometric definition cannot be obtained. The fuel grid elements in the randomly distributed medium fuel elements have non-uniformity on the macro (fuel, cladding and moderator) and also have non-uniformity on the micro (matrix in the fuel pellet, dispersed fuel particles and layered structure in the fuel particles), the macro and micro non-uniformities form double non-uniformities, the spatial self-shielding effect of the double non-uniformities has larger influence on both a thermal group and a resonance energy group, and certain challenge is brought to the traditional neutron calculation method.
For dual non-uniformity of dispersed fuel, the most direct neutron calculation method is to perform rigorous neutron calculations by modeling the random distribution of fuel particles using a monte carlo method based on continuous energy cross-sections. The method can provide a neutron reference for the randomly distributed medium fuel elements, but the calculation cost is huge, and the method is difficult to be applied to time-dependent fuel consumption calculation or multi-physical-field iterative design calculation. Under the current computer development level, the determinism method based on the multi-group structure is still the main method for the neutron design calculation of the randomly distributed medium fuel, but the method lacks the correction of the dual-heterogeneity space self-shielding effect of randomly distributed medium fuel elements, and the calculation is inaccurate.
Disclosure of Invention
The invention aims to solve the technical problem that the existing determinism method based on the multi-group structure cannot correct the dual-heterogeneity space self-shielding effect of the randomly-distributed medium fuel elements, so that the invention provides a dual-heterogeneity space self-shielding effect correction method which is applied to the conventional neutron calculation software in the pressurized water reactor core design, realizes the correction of the dual-heterogeneity space self-shielding effect of the randomly-distributed medium fuel elements and improves the neutron calculation accuracy.
The invention is realized by the following technical scheme:
a dual non-uniformity spatial self-screening effect correction method comprises the following steps:
calculating all neutron numbers escaping from the fuel surface and the neutron numbers entering the adjacent fuel cells to collide without any collision in the moderator after escaping from the fuel surface by a Monte Carlo method to obtain a Danco factor;
acquiring a neutron escape probability, and correcting the neutron escape probability based on the Danco factor so as to correct dual heterogeneity of neutron resonance calculation;
according to the fact that the escape probability of neutrons before and after the neutrons are uniform in the random distribution medium area is unchanged, the random distribution medium area is equivalent to a uniform medium;
and calculating the equivalent section of the homogenizing medium based on the macroscopic sections of the diffusion particles and each sub-area of the matrix, and the corresponding volume fraction and the space self-shielding factor of each sub-area so as to correct the dual heterogeneity of neutron transport calculation.
Further, the calculating of all the neutron numbers escaping from the fuel surface and the neutron numbers entering the adjacent fuel cells without any collision in the moderator after escaping from the fuel surface to generate the Danco factor comprises:
taking all the neutron numbers escaping from the fuel surface as first data;
taking the number of neutrons which enter an adjacent fuel cell to collide without any collision in the moderator after escaping from the fuel surface as second data;
and taking the ratio of the second data to the first data as a Danconf factor.
Further, the calculating the equivalent cross section of the homogenization medium based on the macroscopic cross sections of the diffusion particles and the sub-regions of the matrix, and the volume fraction and the spatial self-screen factor corresponding to the sub-regions comprises:
calculating the equivalent section of the homogenizing medium by an equivalent section calculation formula; the equivalent section calculation formula is specifically
Wherein the content of the first and second substances,
equivalent cross section of the homogenising medium, fjRefers to the volume share of the j sub-area in the whole random distribution medium area, SjSpace self-screen factor, Σ, referring to the j-th sub-areajRefers to the total cross-section of the jth sub-zone,
refers to the total cross section of the j sub-region after considering the spatial self-screen factor.
Further, the equivalent section calculation formula specifically includes a first calculation formula, a second calculation formula, and a third calculation formula;
wherein, the first calculation formula specifically is:
wherein p refers to the escape probability of neutrons in a random distribution medium region, and L refers to the distance which is averagely experienced by each coated particle with the radius of R passing through the coated particle along any flight direction of the neutrons;
the second calculation formula is specifically:
wherein p isjThe first collision probability of neutrons in each sub-area of the random distribution medium area, p the escape probability of neutrons in the random distribution medium area, fjThe volume share of the jth sub-area in the whole random distribution medium area is referred to; wherein the content of the first and second substances,
the third calculation formula is specifically:
wherein S isjSpace self-screen factor, Σ, referring to the j-th sub-areajRefers to the total cross-section of the jth sub-zone,
refers to the total cross section of the j sub-region after considering the spatial self-screen factor.
Further, L in the first calculation formula can be calculated by a fourth formula; wherein the fourth formula is specifically:
thereby obtaining
Wherein R denotes the radius of the coated particle, and F denotes the filling ratio of the coated particle.
A dual non-uniformity spatial self-shadowing correction apparatus, comprising:
the Monte Carlo method processing module is used for calculating all neutron numbers escaping from the fuel surface and the neutron numbers which enter the adjacent fuel grid cells to collide without any collision in the moderator after escaping from the fuel surface by the Monte Carlo method to obtain the Danco factor;
the system comprises a Danco factor correction module, a neutron resonance calculation module and a neutron detection module, wherein the Danco factor correction module is used for acquiring a neutron escape probability and correcting the neutron escape probability based on the Danco factor so as to correct dual heterogeneity of neutron resonance calculation;
the equivalent uniform processing module is used for equating the random distribution medium area to a uniform medium according to the unchanged escape probability of neutrons before and after the neutron is uniform in the random distribution medium area;
and the equivalent section correction module is used for calculating the equivalent section of the homogenizing medium based on the macroscopic sections of the diffusion particles and the sub-regions of the matrix, and the volume fraction and the space self-screen factor corresponding to the sub-regions so as to correct the dual heterogeneity of neutron transport calculation.
Further, the monte carlo method processing module comprises:
a first calculation unit for taking all the neutron numbers escaped from the fuel surface as first data;
a second calculation unit, for using the neutron number which enters the adjacent fuel cells without any collision in the moderator after escaping from the fuel surface and colliding as the second data;
a Danco factor calculating unit for taking a ratio of the second data to the first data as a Danco factor.
Further, the equivalent section correction module is also used for calculating the equivalent section of the homogenizing medium through an equivalent section calculation formula; the equivalent section calculation formula is specifically
Wherein the content of the first and second substances,
equivalent cross section of the homogenising medium, fjRefers to the volume share of the j sub-area in the whole random distribution medium area, SjSpace self-screen factor, Σ, referring to the j-th sub-areajRefers to the total cross-section of the jth sub-zone,
refers to the total cross section of the j sub-region after considering the spatial self-screen factor.
A computer device comprising a memory, a processor and a computer program stored in the memory and executable on the processor, the processor implementing the dual non-uniformity spatial self-shadowing correction method when executing the computer program.
A computer-readable storage medium, in which a computer program is stored which, when being executed by a processor, carries out the above-mentioned dual-inhomogeneity spatial self-shadowing correction method.
According to the dual-heterogeneity space self-shielding effect correction method provided by the invention, through a Monte Carlo method, the number of all neutrons escaping from the fuel surface and the number of neutrons entering adjacent fuel cells to collide without any collision in a moderator are calculated, and a Danco factor is obtained; acquiring neutron escape probability, and correcting the neutron escape probability based on a Danco factor so as to correct dual heterogeneity of neutron resonance calculation; according to the fact that the escape probability of neutrons before and after the neutrons are uniform in the random distribution medium area is unchanged, the random distribution medium area is equivalent to a uniform medium; and calculating the equivalent section of the homogenized medium based on the macroscopic sections of the dispersion particles and each sub-area of the matrix, and the corresponding volume fraction and the space self-shielding factor of each sub-area to correct the dual heterogeneity of the neutron transport calculation, realize the correction of the dual heterogeneity space self-shielding effect of the randomly distributed medium fuel element, and improve the neutron calculation accuracy.
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 flowchart of a dual non-uniformity spatial self-screening effect correction method according to the present invention.
FIG. 2 is a three-dimensional physical model of neutron first collision probability in the embodiment of the present invention.
FIG. 3 is a two-dimensional physical model of neutron first collision probability in the embodiment of the present invention.
FIG. 4 is a schematic block diagram of a dual non-uniformity spatial self-shadowing correction apparatus according to the present invention.
FIG. 5 is a schematic diagram of the computer apparatus of the present invention.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
Example 1
As shown in fig. 1, the present invention provides a dual non-uniformity spatial self-screening effect correction method, which specifically includes the following steps:
s10: and calculating all neutron numbers escaping from the fuel surface and the neutron numbers entering the adjacent fuel cells to collide without any collision in the moderator after escaping from the fuel surface by a Monte Carlo method to obtain the Danco factor.
Specifically, the number of all neutrons escaping from the fuel surface is counted as first data, the number of neutrons which do not pass through any collision in the moderator after escaping from the fuel surface and enter an adjacent fuel cell to collide is counted as second data, and the ratio of the second data to the first data is used as a Dankov factor.
S20: and acquiring the neutron escape probability, and correcting the neutron escape probability based on the Danco factor so as to correct the dual heterogeneity of the neutron resonance calculation.
Specifically, the neutron escape probability is obtained, and is corrected through the escape probability multiplied by the Dankff factor, so as to correct the dual heterogeneity of the neutron resonance calculation.
S30: and according to the fact that the escape probability of the neutrons before and after the neutrons are uniform in the random distribution medium area is unchanged, the random distribution medium area is equivalent to a uniform medium.
S40: and calculating the equivalent section of the homogenizing medium based on the macroscopic sections of the diffusion particles and each sub-area of the matrix, and the corresponding volume fraction and the space self-shielding factor of each sub-area so as to correct the dual heterogeneity of neutron transport calculation.
Further, the equivalent section of the homogenization medium is calculated through an equivalent section calculation formula. The equivalent section calculation formula is
Wherein the content of the first and second substances,
equivalent cross section of the homogenising medium, fjRefers to the volume share of the j sub-area in the whole random distribution medium area, SjSpace self-screen factor, Σ, referring to the j-th sub-areajRefers to the total cross-section of the jth sub-zone,
refers to the total cross section of the j sub-region after considering the spatial self-screen factor.
Further, the equivalent section calculation formula specifically includes a first calculation formula, a second calculation formula, and a third calculation formula.
Wherein, the first calculation formula specifically is:
wherein p refers to the escape probability of neutrons in a randomly distributed medium area, and L refers to the average probability of neutrons passing through a coated particle with radius R along any flight direction of the neutronsDistance.
L in the first calculation formula can be calculated by a fourth formula. Wherein the fourth formula is specifically:
thereby obtaining
Wherein R denotes the radius of the coated particle, and F denotes the filling ratio of the coated particle.
The second calculation formula is specifically:
wherein p isjThe first collision probability of neutrons in each sub-area of the random distribution medium area, p the escape probability of neutrons in the random distribution medium area, fjRefers to the volume share of the j-th sub-zone in the whole random distribution medium zone. Wherein the content of the first and second substances,
the third calculation formula is specifically:
wherein S isjSpace self-screen factor, Σ, referring to the j-th sub-areajRefers to the total cross-section of the jth sub-zone,
refers to the total cross section of the j sub-region after considering the spatial self-screen factor.
Specifically, a first collision probability physical model as shown in fig. 2 is established, wherein neutrons are uniformly emitted from the bottom surface of a cylinder with a radius R and parallel to the axis of the cylinder, and pass through the coated particles at the center of the cylinder. Considering symmetry, the three-dimensional physical model may be equivalent to a two-dimensional computational model as shown in FIG. 3.
In FIG. 3, let lmRepresenting the length of the left semi-planar neutron trajectory through the substrate, ljRepresenting the length of the left semi-planar neutron trajectory through the jth sub-zone of the coated particle. Neutrons pass through the graphite matrixAnd the probability p of a particle being coated without collision is:
wherein u is sin2Theta, u being an intermediate variable, sigmamDenotes the total cross-section of the mth subregion,/m(u) optical distance of neutron through left half-plane to mth sub-zone, ΣjDenotes the total cross-section of the j-th subregion,/j(u) refers to the optical distance of the neutron through the left half-plane to the j sub-zone, R refers to the radius of the coated particle, x refers to the variation of the radius of the j sub-zone, lj(x) Refers to the optical distance of the neutron through the left half plane to the j sub-region.
The probability of the first collision of the neutron with the i-th area of the coated particle is as follows:
wherein r isiDenotes the radius of the j-th sub-region, lm(x) Refers to the optical distance of the neutron from the m-th sub-zone through the left half-plane,/i(x) Refers to the optical distance of the neutron through the left half plane to the ith sub-zone.
When the random medium region contains a plurality of coating particle types, the number of the coating particle is marked as k, and the number of each subarea of the coating particle is marked as j. To simplify the problem, assuming negligible mutual shielding effect between the coated particles, the following calculation strategy is adopted:
(1) and (3) according to the volume share of each type of coating particles, the matrix is distributed to each type of coating particles according to the volume share. The volume fraction of the particles which are evenly distributed to the kth coating particles is
Wherein f iskRepresenting the volume fraction occupied by the kth coated particle.
(2) Through the model given in fig. 3, the first collision probability of the kth type of coating particles in each sub-region is independently solved, and the effective cross section of the kth type of coating particles is calculated, so that the homogenization cross section of the whole random medium region is obtained. Wherein, 1 refers to a substrate, 2 refers to a first dispersed particle subarea, 3 refers to a second dispersed particle subarea, and 4 refers to a third dispersed particle subarea.
In the embodiment, firstly, a Dancoff (Dancoff) factor is obtained by modeling calculation by using an MCNP (Monte Carlo) method, a source code of a resonance part in a traditional pressurized water reactor calculation program is modified, and the Dancoff factor is used as an input parameter to correct neutron resonance calculation; the derivation process described above is then programmed using C + +. And correcting the cross section of each subarea of the output set by resonance calculation before the beginning of transport calculation, and putting the cross section into an internal program of a fuel consumption calculation cycle, wherein each fuel consumption step is corrected. Through calculation verification of an FCM (full ceramic micro-encapsulation) fuel assembly containing dispersed fuel, the calculation deviation of Kinf (infinite multiplication factor) and RMC (Reactor Monte Carlo code) in the burn-up process can be kept within 5 per mill, and the relative power deviation of each grid element in the assembly is within 10 per mill, so that the correction method can be used for correcting the conventional pressurized water Reactor calculation program to enable the pressurized water Reactor to have the calculation function of a double non-uniform system.
Example 2
As shown in fig. 4, the present embodiment is different from embodiment 1 in that a dual non-uniformity spatial self-shadowing correction apparatus is provided, which includes:
and the Monte Carlo method processing module 10 is used for calculating all neutron numbers escaping from the fuel surface and the neutron numbers entering the adjacent fuel cells to collide without any collision in the moderator after escaping from the fuel surface by the Monte Carlo method to obtain the Danco-ff factor.
And the Danco factor correction module 20 is configured to obtain the neutron escape probability, and correct the neutron escape probability based on the Danco factor to correct dual non-uniformity of neutron resonance calculation.
And the equivalent uniform processing module 30 is used for equating the randomly distributed medium region into a uniform medium according to the unchanged escape probability of the neutrons before and after the neutron is uniform in the randomly distributed medium region.
And the equivalent section correction module 40 is used for calculating the equivalent section of the homogenizing medium based on the macroscopic sections of the diffusion particles and the sub-regions of the matrix, and the volume fraction and the space self-screen factor corresponding to the sub-regions so as to correct the dual heterogeneity of neutron transport calculation.
Further, the channel dynamic opening and closing processing module 10 includes a data channel determining unit to be determined, an external link processing unit, and an effective data channel determining unit.
The Monte Carlo method processing module comprises a first calculating unit, a second calculating unit and a Danco factor calculating unit.
And the first calculation unit is used for taking all neutron numbers escaping from the fuel surface as first data.
And the second calculation unit is used for taking the number of neutrons which enter the adjacent fuel cells without any collision in the moderator after escaping from the fuel surface as second data.
And the Danco factor calculating unit is used for taking the ratio of the second data to the first data as the Danco factor.
Further, the equivalent cross section correction module 40 is further configured to calculate an equivalent cross section of the homogenization medium through an equivalent cross section calculation formula. The equivalent section calculation formula is
Wherein the content of the first and second substances,
equivalent cross section of the homogenising medium, fjRefers to the volume share of the j sub-area in the whole random distribution medium area, SjSpace self-screen factor, Σ, referring to the j-th sub-areajRefers to the total cross-section of the jth sub-zone,
refers to the total cross section of the j sub-region after considering the spatial self-screen factor.
Further, the equivalent section calculation formula specifically includes a first calculation formula, a second calculation formula, and a third calculation formula.
Wherein the first computing unitThe formula is specifically as follows:
wherein p refers to the escape probability of neutrons in a random distribution medium area, and L refers to the distance which is averagely experienced by each coated particle with the radius of R along any flight direction of the neutrons.
The second calculation formula is specifically:
wherein p isjThe first collision probability of neutrons in each sub-area of the random distribution medium area, p the escape probability of neutrons in the random distribution medium area, fjRefers to the volume share of the j-th sub-zone in the whole random distribution medium zone. Wherein the content of the first and second substances,
the third calculation formula is specifically:
wherein S isjSpace self-screen factor, Σ, referring to the j-th sub-areajRefers to the total cross-section of the jth sub-zone,
refers to the total cross section of the j sub-region after considering the spatial self-screen factor.
Further, L in the first calculation formula can be calculated by a fourth formula. Wherein the fourth formula is specifically:
thereby obtaining
Wherein R denotes the radius of the coated particle, and F denotes the filling ratio of the coated particle.
For specific limitation of the dual-nonuniformity-based spatial self-screening effect correction device, reference may be made to the above limitation on a dual-nonuniformity spatial self-screening effect correction method, which is not described herein again. The modules in the dual non-uniformity based spatial self-screen effect correction device can be wholly or partially realized by software, hardware and a combination thereof. The modules can be embedded in a hardware form or independent from a processor in the computer device, and can also be stored in a memory in the computer device in a software form, so that the processor can call and execute operations corresponding to the modules.
Example 3
The embodiment provides a computer device, which may be a server, and the internal structure diagram of the computer device may be as shown in fig. 5. The computer device includes a processor, a memory, a network interface, and a database connected by a system bus. Wherein the processor of the computer device is configured to provide computing and control capabilities. The memory of the computer device includes a computer readable storage medium, an internal memory. The computer readable storage medium stores an operating system, a computer program, and a database. The internal memory provides an environment for the operation of an operating system and computer programs in the computer-readable storage medium. The database of the computer device is used for storing data involved in a dual non-uniformity spatial self-screen effect correction method. The network interface of the computer device is used for communicating with an external terminal through a network connection. The computer program is executed by a processor to implement a dual non-uniformity spatial self-shadowing correction method.
The present embodiment provides a computer device, 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 computer program, the processor implements the steps of the dual non-uniformity spatial self-screen effect correction method in the above embodiments, such as step 10 to step S40 shown in fig. 1. Alternatively, the processor, when executing the computer program, implements the functions of the modules/units of the dual non-uniformity spatial self-shadowing correction apparatus in the above embodiments, such as the functions of the modules 10 to 40 shown in fig. 4. To avoid repetition, further description is omitted here.
Example 4
In one embodiment, a computer-readable storage medium is provided, having a computer program stored thereon, which when executed by a processor implements the steps of a dual non-uniformity spatial self-screen effect correction method in the above-described embodiments, such as the steps S10-S40 shown in fig. 1. Alternatively, the processor, when executing the computer program, implements the functions of the modules/units in the embodiment of the dual non-uniformity spatial self-shadowing correction apparatus, such as the functions of the modules 10 to 40 shown in fig. 4. To avoid repetition, further description is omitted here.
It will be understood by those skilled in the art that all or part of the processes of the methods of the embodiments described above can be implemented by hardware instructions of a computer program, which can be stored in a non-volatile computer-readable storage medium, and when executed, can include the processes of the embodiments of the methods described above. Any reference to memory, storage, database, or other medium used in the embodiments provided herein may include non-volatile and/or volatile memory, among others. Non-volatile memory can include read-only memory (ROM), Programmable ROM (PROM), Electrically Programmable ROM (EPROM), Electrically Erasable Programmable ROM (EEPROM), or flash memory. Volatile memory can include Random Access Memory (RAM) or external cache memory. By way of illustration and not limitation, RAM is available in a variety of forms such as Static RAM (SRAM), Dynamic RAM (DRAM), Synchronous DRAM (SDRAM), Double Data Rate SDRAM (DDRSDRAM), Enhanced SDRAM (ESDRAM), Synchronous Link DRAM (SLDRAM), Rambus Direct RAM (RDRAM), direct bus dynamic RAM (DRDRAM), and memory bus dynamic RAM (RDRAM).
It will be apparent to those skilled in the art that, for convenience and brevity of description, only the above-mentioned division of the functional units and modules is illustrated, and in practical applications, the above-mentioned function distribution may be performed by different functional units and modules according to needs, that is, the internal structure of the apparatus is divided into different functional units or modules to perform all or part of the above-mentioned functions.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, 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 (10)
1. A dual non-uniformity spatial self-screening effect correction method is characterized by comprising the following steps:
calculating all neutron numbers escaping from the fuel surface and the neutron numbers entering the adjacent fuel cells to collide without any collision in the moderator after escaping from the fuel surface by a Monte Carlo method to obtain a Danco factor;
acquiring a neutron escape probability, and correcting the neutron escape probability based on the Danco factor so as to correct dual heterogeneity of neutron resonance calculation;
according to the fact that the escape probability of neutrons before and after the neutrons are uniform in the random distribution medium area is unchanged, the random distribution medium area is equivalent to a uniform medium;
and calculating the equivalent section of the homogenizing medium based on the macroscopic sections of the diffusion particles and each sub-area of the matrix, and the corresponding volume fraction and the space self-shielding factor of each sub-area so as to correct the dual heterogeneity of neutron transport calculation.
2. The dual non-uniformity spatial self-shadowing correction method of claim 1, wherein the calculating of all neutron numbers escaping from the fuel surface and the neutron numbers entering the neighboring fuel cells without any collision in the moderator after escaping from the fuel surface to collide with each other, resulting in a Danco factor, comprises:
taking all the neutron numbers escaping from the fuel surface as first data;
taking the number of neutrons which enter an adjacent fuel cell to collide without any collision in the moderator after escaping from the fuel surface as second data;
and taking the ratio of the second data to the first data as a Danconf factor.
3. The dual non-uniformity spatial self-shielding effect correction method according to claim 1, wherein the calculating the equivalent cross section of the homogenization medium based on the macroscopic cross sections of the sub-regions of the dispersed particles and the matrix, and the volume fraction and the spatial self-shielding factor corresponding to the sub-regions comprises:
calculating the equivalent section of the homogenizing medium by an equivalent section calculation formula; the equivalent section calculation formula is specifically
Wherein the content of the first and second substances,
equivalent cross section of the homogenising medium, fjRefers to the volume share of the j sub-area in the whole random distribution medium area, SjSpace self-screen factor, Σ, referring to the j-th sub-areajRefers to the total cross-section of the jth sub-zone,
refers to the total cross section of the j sub-region after considering the spatial self-screen factor.
4. The dual non-uniformity spatial self-shadowing correction method according to claim 3, wherein the equivalent cross-section calculation formula specifically includes a first calculation formula, a second calculation formula, and a third calculation formula;
wherein, the first calculation formula specifically is:
wherein p refers to the escape probability of neutrons in a random distribution medium region, and L refers to the distance which is averagely experienced by each coated particle with the radius of R passing through the coated particle along any flight direction of the neutrons;
the second calculation formula is specifically:
wherein p isjThe first collision probability of neutrons in each sub-area of the random distribution medium area, p the escape probability of neutrons in the random distribution medium area, fjThe volume share of the jth sub-area in the whole random distribution medium area is referred to; wherein the content of the first and second substances,
the third calculation formula is specifically:
wherein S isjSpace self-screen factor, Σ, referring to the j-th sub-areajRefers to the total cross-section of the jth sub-zone,
refers to the total cross section of the j sub-region after considering the spatial self-screen factor.
5. The dual non-uniformity spatial self-shadowing correction method of claim 4, wherein L in the first calculation formula is calculated by a fourth formula; wherein the fourth formula is specifically:
thereby obtaining
Wherein R denotes the radius of the coated particle, and F denotes the filling ratio of the coated particle.
6. A dual non-uniformity spatial self-shadowing correction apparatus, comprising:
the Monte Carlo method processing module is used for calculating all neutron numbers escaping from the fuel surface and the neutron numbers which enter the adjacent fuel grid cells to collide without any collision in the moderator after escaping from the fuel surface by the Monte Carlo method to obtain the Danco factor;
the system comprises a Danco factor correction module, a neutron resonance calculation module and a neutron detection module, wherein the Danco factor correction module is used for acquiring a neutron escape probability and correcting the neutron escape probability based on the Danco factor so as to correct dual heterogeneity of neutron resonance calculation;
the equivalent uniform processing module is used for equating the random distribution medium area to a uniform medium according to the unchanged escape probability of neutrons before and after the neutron is uniform in the random distribution medium area;
and the equivalent section correction module is used for calculating the equivalent section of the homogenizing medium based on the macroscopic sections of the diffusion particles and the sub-regions of the matrix, and the volume fraction and the space self-screen factor corresponding to the sub-regions so as to correct the dual heterogeneity of neutron transport calculation.
7. The dual non-uniformity spatial self-shadowing correction apparatus of claim 6, wherein the monte carlo method processing module comprises:
a first calculation unit for taking all the neutron numbers escaped from the fuel surface as first data;
a second calculation unit, for using the neutron number which enters the adjacent fuel cells without any collision in the moderator after escaping from the fuel surface and colliding as the second data;
a Danco factor calculating unit for taking a ratio of the second data to the first data as a Danco factor.
8. The dual non-uniformity spatial self-shielding effect correction device according to claim 6, wherein the equivalent cross section correction module is further configured to calculate an equivalent cross section of the homogenization medium through an equivalent cross section calculation formula; the equivalent section calculation formula is specifically
Wherein the content of the first and second substances,
equivalent cross section of the homogenising medium, fjRefers to the volume share of the j sub-area in the whole random distribution medium area, SjSpace self-screen factor, Σ, referring to the j-th sub-areajRefers to the total cross-section of the jth sub-zone,
refers to the total cross section of the j sub-region after considering the spatial self-screen factor.
9. A computer device comprising a memory, a processor and a computer program stored in the memory and executable on the processor, wherein the processor implements the dual non-uniformity spatial self-shadowing correction method of any of claims 1 to 5 when executing the computer program.
10. A computer-readable storage medium, in which a computer program is stored, which, when being executed by a processor, implements the dual non-uniformity spatial self-shadowing correction method according to any one of claims 1 to 5.
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