CN115376711B - Method and system for detecting boron 10 coating distribution of fuel rod of pressurized water reactor nuclear power plant - Google Patents
Method and system for detecting boron 10 coating distribution of fuel rod of pressurized water reactor nuclear power plant Download PDFInfo
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- 238000009826 distribution Methods 0.000 title claims abstract description 95
- ZOXJGFHDIHLPTG-BJUDXGSMSA-N Boron-10 Chemical compound [10B] ZOXJGFHDIHLPTG-BJUDXGSMSA-N 0.000 title claims abstract description 93
- 239000000446 fuel Substances 0.000 title claims abstract description 85
- 238000000034 method Methods 0.000 title claims abstract description 53
- 239000011248 coating agent Substances 0.000 title claims abstract description 34
- 238000000576 coating method Methods 0.000 title claims abstract description 34
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 33
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 claims abstract description 43
- 229910052796 boron Inorganic materials 0.000 claims abstract description 43
- 238000001514 detection method Methods 0.000 claims abstract description 39
- 230000007704 transition Effects 0.000 claims description 25
- 230000008859 change Effects 0.000 claims description 23
- 238000004364 calculation method Methods 0.000 claims description 15
- 230000008030 elimination Effects 0.000 claims description 9
- 238000003379 elimination reaction Methods 0.000 claims description 9
- 238000004590 computer program Methods 0.000 claims description 6
- 238000005520 cutting process Methods 0.000 claims description 4
- 238000012935 Averaging Methods 0.000 claims description 3
- 238000003860 storage Methods 0.000 claims description 3
- 230000008569 process Effects 0.000 abstract description 8
- 238000004458 analytical method Methods 0.000 abstract description 4
- 238000012545 processing Methods 0.000 abstract description 3
- 230000009897 systematic effect Effects 0.000 abstract description 3
- 238000004519 manufacturing process Methods 0.000 abstract description 2
- 230000004913 activation Effects 0.000 description 3
- 230000000712 assembly Effects 0.000 description 3
- 238000000429 assembly Methods 0.000 description 3
- 238000013461 design Methods 0.000 description 3
- 238000013213 extrapolation Methods 0.000 description 3
- 239000008188 pellet Substances 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000005253 cladding Methods 0.000 description 1
- 238000007596 consolidation process Methods 0.000 description 1
- 230000003111 delayed effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000005251 gamma ray Effects 0.000 description 1
- 230000006872 improvement Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000010606 normalization Methods 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
- 230000001105 regulatory effect Effects 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- High Energy & Nuclear Physics (AREA)
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Abstract
The invention belongs to the technical field of coating distribution detection, and provides a method and a system for detecting the coating distribution of boron 10 on fuel rods of a pressurized water reactor nuclear power plant, which are used for eliminating the non-uniformity of detection data based on the enrichment degree detection process and the result of axial boron-coated fuel rods of the pressurized water reactor nuclear power plant in current production, and obtaining the distribution condition of the axial boron 10 and the axial distribution slope of the boron 10 according to the counting points of ideal scanning shapes obtained after the non-uniformity is eliminated, the counting of the counting points of the average rods of multiple batches and the reference content reference value of the boron 10; the detection data is subjected to systematic analysis processing, and the obtained axial boron 10 distribution condition and the boron 10 axial distribution slope can be used for judging whether the produced axial boron-coated fuel rod of the pressurized water reactor nuclear power plant is qualified or not, so that the detection process of the axial boron-coated fuel rod is supported and is used for a neutron model of a reactor core of the nuclear power plant.
Description
Technical Field
The invention belongs to the technical field of coating distribution detection, and particularly relates to a method and a system for detecting the coating distribution of fuel rods boron 10 in a pressurized water reactor nuclear power plant.
Background
Current advanced three generation pressurized water reactor core designs all employ fuel assemblies with boron 10 (B-10) coated fuel pellet surfaces. By coating the B-10 on the surface of the fuel pellet, the local reactivity of the reactor can be effectively regulated, and excessive neutron poison residues are not introduced, so that the reactor core design of the pressurized water reactor nuclear power plant is optimized in terms of safety and economy. In general, an axially boron-coated fuel rod is divided into three regions, a low enrichment region, a transition region, and an axially boron-coated region. The low enrichment region is a region with slightly lower enrichment degree of the core blocks at the two ends of the fuel rod, such as a region with the enrichment degree of 0-4.5w/o under any range value; the axial boron-coated area is a high-enrichment core block area for coating boron on the surface of the middle section of the fuel rod, such as an area with enrichment of 0.5-5w/o under any value range; the transition zone is a transition zone between the low enrichment zone and the axial boron-coated zone, and the schematic diagram of each zone is shown in figure 1.
Because the pellets coated with the B-10 coating on the surface are easy to rub with the cladding during the assembly process of the fuel rod, the thickness of the B-10 coating is uneven, and the axial B-10 content distribution of the fuel rod is uneven. Too large B-10 axial distribution non-uniformity can cause core power distribution to shift, affecting reactor power distribution control. Therefore, the uniformity of B-10 coating in the currently produced axial boron-coated fuel assemblies needs to be detected, the uniformity of B-10 coating is ensured to meet the design requirements, and the axial distribution data of B-10 is formed for the neutron model of the core of the nuclear power plant.
The inventor finds that the detection data of the fuel rod is mainly obtained by a neutron activation method at present, but the detection data is not subjected to systematic analysis treatment in the existing method, so that the detection technology of the axial boron-coated fuel rod cannot be well supported, and the detection technology is used for a neutron model of a reactor core of a nuclear power plant.
Disclosure of Invention
The invention aims to solve the problems and provides a method and a system for detecting the boron 10 coating distribution of a fuel rod of a pressurized water reactor nuclear power plant.
In order to achieve the above object, the present invention is realized by the following technical scheme:
in a first aspect, the invention provides a method for detecting the boron 10 coating distribution of a fuel rod of a pressurized water reactor nuclear power plant, which comprises the following steps:
acquiring detection data;
carrying out non-uniformity elimination on the detection data to obtain the count of each counting point of an ideal scanning shape, the count of each counting point of a plurality of batches of average rods and a reference value of the base content of boron 10;
calculating the difference between the count of each counting point of the ideal scanning shape and the count of each counting point of the average rod of a plurality of batches, and dividing the obtained difference by the reference value of the basic content of the boron 10 and the change factor of the boron 10 to obtain the distribution condition of the axial boron 10;
based on the distribution condition of the axial boron 10, the axial distribution slope of the boron 10 is obtained by adopting a least square method.
Further, selecting a bottom low enrichment region of each fuel rod; searching a point with the minimum counting change rate in the low enrichment region by using a least square method; the point with the minimum counting change rate is used as a normalized reference value after being averaged with the adjacent points on the two sides of the point; dividing all the counts of the fuel rods by the reference value to obtain the counts of each counting point of the ideal scanning shape.
Further, the counts at the same counting points of the fuel rods of each batch are homogenized, and the counts of each counting point of the average rods of a plurality of batches are obtained.
Further, the data obtained by cutting off the distance affected by the transition period at each end of the axial boron-coated region is averaged to obtain an average count obtained by cutting off the distance affected by the transition period at each end of the axial boron-coated region on the average rod.
Further, after the axial boron 10 distribution condition is obtained, the boron 10 distribution between the distance points influenced by the transition period and the distance points influenced by twice the transition period at the two ends of the axial boron-coated region is calculated by using a least square method, and the boron 10 distribution in the influence region of the transition period is extrapolated.
Further, the change factor of boron 10 refers to the degree of change in the count of the enrichment of the axially boron-coated fuel rod.
Further, based on the distribution condition of the axial boron 10, the axial distribution slope of the boron 10 is calculated by adopting a least square method:
wherein Bslope is the slope of the boron 10 axial distribution; n is the total count point; b (B) dis Distributed for axial boron 10; mesh is the interval between counting points; i is the number of the count point.
In a second aspect, the invention also provides a system for detecting the boron 10 coating distribution of a fuel rod of a pressurized water reactor nuclear power plant, which comprises:
a data acquisition module configured to: acquiring detection data;
a non-uniformity elimination module configured to: carrying out non-uniformity elimination on the detection data to obtain the count of each counting point of an ideal scanning shape, the count of each counting point of a plurality of batches of average rods and a reference value of the base content of boron 10;
calculating the difference between the count of each counting point of the ideal scanning shape and the count of each counting point of the average rod of a plurality of batches, dividing the obtained difference by boron, dividing the obtained difference by a reference value of the basic content of boron 10 and a change factor of the boron 10, and obtaining the distribution condition of the axial boron 10;
a distribution slope calculation module configured to: based on the distribution condition of the axial boron 10, the axial distribution slope of the boron 10 is obtained by adopting a least square method.
In a third aspect, the present invention also provides a computer readable storage medium having stored thereon a computer program which when executed by a processor implements the steps of the method for detecting a coating distribution of fuel rods boron 10 in a pressurized water reactor nuclear power plant according to the first aspect.
In a fourth aspect, the present invention also provides an electronic device, including a memory, a processor, and a computer program stored in the memory and capable of running on the processor, where the processor implements the steps of the method for detecting the boron 10 coating distribution of the fuel rod in the pressurized water reactor nuclear power plant according to the first aspect when executing the program.
Compared with the prior art, the invention has the beneficial effects that:
the method is based on the enrichment degree detection process and the result of the axial boron-coated fuel rod of the current production pressurized water reactor nuclear power plant, the non-uniformity of detection data is eliminated, and the distribution condition of the axial boron 10 and the axial distribution slope of the boron 10 are obtained according to the count of each count point of an ideal scanning shape, the count of each count point of a plurality of batches of average rods and the reference value of the basic content of the boron 10, which are obtained after the non-uniformity is eliminated; the detection data is subjected to systematic analysis processing, and the obtained axial boron 10 distribution condition and the boron 10 axial distribution slope can be used for judging whether the produced axial boron-coated fuel rod of the pressurized water reactor nuclear power plant is qualified or not, so that the detection process of the axial boron-coated fuel rod is supported and is used for a neutron model of a reactor core of the nuclear power plant.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments and are incorporated in and constitute a part of this specification, illustrate and explain the embodiments and together with the description serve to explain the embodiments.
FIG. 1 is a schematic view of the axial boron-coated fuel rod of example 1 of the present invention;
FIG. 2 is a flow chart of embodiment 1 of the present invention;
FIG. 3 is an average rod count after fuel rod consolidation of example 2 of the present invention;
FIG. 4 is an average count of the distance between each end of the axially boron-coated region of the average rod of example 2 after the transition period;
fig. 5 is a graph showing the calculated value range of example 2 of the present invention.
The specific embodiment is as follows:
the invention will be further described with reference to the drawings and examples.
It should be noted that the following detailed description is exemplary and is intended to provide further explanation of the present application. Unless defined otherwise, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this application belongs.
Example 1:
the embodiment provides a method for detecting the boron 10 coating distribution of a fuel rod of a pressurized water reactor nuclear power plant, which comprises the following steps:
acquiring detection data;
carrying out non-uniformity elimination on the detection data to obtain the count of each counting point of an ideal scanning shape, the count of each counting point of a plurality of batches of average rods and a reference value of the base content of boron 10;
calculating the difference between the count of each counting point of the ideal scanning shape and the count of each counting point of the average rod of a plurality of batches, and dividing the calculated difference by the reference value of the basic content of the boron 10 and the change factor of the boron 10 to obtain the distribution condition of the axial boron 10;
based on the distribution condition of the axial boron 10, the axial distribution slope of the boron 10 is obtained by adopting a least square method.
When the detection data is obtained, the detection data can be obtained based on the enrichment degree detection process and the result of the axial boron-coated fuel rod of the pressurized water reactor nuclear power plant at present, for example, the detection data of the fuel rod can be obtained by a neutron activation method at present; specifically, the neutron activation method is to irradiate the external cf-252 neutron source to cause the fissile material in the fuel rod to generate fission. The delayed gamma rays in the fission products are measured by a detector, a photomultiplier tube in the detector converts gamma ray signals into pulse electric signals, and the pulse electric signals are collected at fixed time and converted into counting rate. The count rate is recorded along the length of the fuel rod as raw data of the fuel rod enrichment information.
Selecting a bottom low enrichment region of each fuel rod; searching a point with the minimum counting change rate in the low enrichment region by using a least square method; the point with the minimum counting change rate is used as a normalized reference value after being averaged with the adjacent points on the two sides of the point; dividing all the counts of the fuel rods by the reference value to obtain the counts of each counting point of the ideal scanning shape.
Specifically, in order to consider the fluctuation of the count of the detection system, the least square method of the low enrichment area at the bottom of each fuel rod can be selected to find the point with the minimum counting change rate in the area, the point is averaged with the counts of adjacent points at two sides and then used as a normalized reference value, and all the counts of the fuel rods are divided by the value to obtain the counts of all the counting points in an ideal scanning shape. It will be appreciated that the rate of change represents an overall characteristic of the boron-coated condition of the component.
The least square method of the change rate has the following calculation formula:
wherein t is i+2n-1 、t i+2n-2 、t i+2 And t i+1 Counts of the positions of points i+2n-1, i+2n-2, i+2 and i+1, respectively.
And homogenizing the counts of the same counting points of the fuel rods of each batch to obtain the counts of each counting point of the average rods of a plurality of batches.
Specifically, due to the non-uniformity of mechanical movement of the detection device during the detection process, the distance between detection points on each fuel rod has small difference; the count redistribution condition of the fuel rods after combination is obtained by homogenizing the counts of the same counting points of the fuel rods in each batch, so that the counts of all counting points of the average rod are obtained, and the subsequent calculation and analysis are carried out based on the counts of all counting points of the average rod.
And averaging the data of which the two ends of the axial boron-coated area are cut off by the distance influenced by the transition period to obtain the average count of which the two ends of the axial boron-coated area are cut off by the distance influenced by the transition period on the average rod.
Specifically, in order to calculate the variation distribution of the B-10 in the axial direction of the axial boron-coated fuel rod of the pressurized water reactor nuclear power plant, the reference value is required to be used for representing the reference content of the B-10; because the counts at the two ends of the axial boron-coated area have transition areas with a certain length, the data of the two ends of the area, which are cut off by the distance L0 influenced by the transition period, are directly averaged to be used as the reference value AVG of the base content of B-10, namely the average counts of the two ends of the axial boron-coated area on the average rod, which are cut off by the distance influenced by the transition period. In addition, after L0 is truncated at each end of the area, the count of each point is set as the reference value of the area, namely the ideal scanning shape ISP, so as to calculate the B-10 distribution.
After the axial boron 10 distribution condition is obtained, the boron 10 distribution between the distance points influenced by the transition period and the distance points influenced by twice the transition period at the two ends of the axial boron-coated region is calculated by using a least square method, and the boron 10 distribution in the region influenced by the transition period is extrapolated.
Specifically, the B-10 change factor alpha represents the change degree of the front and back counts of the axial boron-coated fuel rods with the same enrichment degree, so that the conversion from the axial counts of the fuel rods to the axial distribution of B-10 can be completed by utilizing the B-10 change factor alpha according to the calculation result of an ideal scanning shape; the B-10 distribution is calculated as follows:
wherein: ISP counts for each count point of the ideal scan shape; AGS is the count of each counting point of the average rod; AVG is average count after each cut-off distance affected by transition period at two ends of axial boron-coated area on average rod; alpha is a B-10 change factor; i is the number of the count point.
Based on the calculation result of the axial boron 10 distribution condition, the axial distribution slope (/%cm) of the boron 10 is calculated by adopting a least square method and is as follows:
wherein Bslope is the slope of the boron 10 axial distribution; n is the total count point; b (B) dis Distributed for axial boron 10; mesh is the interval between counting points; i is the number of the count point.
And based on the calculation result of the B-10 distribution of the fuel rods in each batch, carrying out weight summation according to the number of the fuel rods contained in each batch, and calculating to obtain the total B-10 distribution. The same slope calculation method is adopted to calculate the total B-10 slope.
Considering that the overall B-10 distribution is a distance L affected by the transition period excluding the end-cuts 0 For calculation, a complete B-10 distribution of the axially boron-coated region, so that extrapolation of the B-10 distribution at both ends is required. Specifically, in extrapolation calculation, the least square method may be used to calculate the two ends L 0 ～2L 0 Extrapolation of the relation of B-10 distribution over cm by 0-L 0 Cm of B-10 distribution.
And according to the division of the axial segments of the core design program, carrying out average calculation on the B-10 distribution on the axial boron-coated region according to the integral of the segment length, and finally carrying out normalization processing on the calculation results of all segments of the axial boron-coated region to obtain the final B-10 axial distribution SHAPE SHAPE. For the segments of the non-axial boron-coated region, the axially distributed SHAPE SHAPE takes a value of 0.0.
The slope and the axial distribution shape of the axial boron-coated fuel rod B-10 are obtained through calculation, and the method can be used for judging whether the produced axial boron-coated fuel rod of the pressurized water reactor nuclear power plant is qualified or not, so that the detection process of the support fuel rod is used for a neutron model of a reactor core of the nuclear power plant.
Implementation example 2:
taking a test result file of a certain unit fuel assembly as an example, the method for calculating the slope of the axial boron-coated fuel rod B-10 in the embodiment 1 is explained.
Calculating average rods and reference values of all batches of fuel rods; taking a batch of fuel rods as an example, the average rod count of the batch of fuel rods after being combined is shown in fig. 3, and the abscissa of fig. 3 is the distance from the bottom to the top of the fuel rods, ranging from 0 cm to 425 cm.
Calculating the distribution and slope of each batch of fuel rods B-10; taking a certain batch of fuel rods as an example, an average count of the average rods of the batch after the distance affected by the transition period is cut off at each end of the axial boron-coated area is obtained, and the distribution situation is shown in fig. 4.
The slope of the batch of fuel rods B-10 was 0.004685%/cm as calculated according to the formula.
The overall fuel rod B-10 distribution and slope were calculated. The slope of the unit fuel assembly B-10 is obtained through calculation: 0.003218%/cm. The unit fuel assembly B-10 is also known to have a mass of 14.6 g/assembly. It can be seen from fig. 5 that the calculated values are within the acceptable limits, and that the B-10 coating conditions in the unit fuel assemblies are acceptable.
Example 3:
the embodiment provides a pressurized water reactor nuclear power plant fuel rod boron 10 coating distribution detection system, which comprises:
a data acquisition module configured to: acquiring detection data;
a non-uniformity elimination module configured to: carrying out non-uniformity elimination on the detection data to obtain the count of each counting point of an ideal scanning shape, the count of each counting point of a plurality of batches of average rods and a reference value of the base content of boron 10;
calculating the difference between the count of each counting point of the ideal scanning shape and the count of each counting point of the average rod of a plurality of batches, dividing the obtained difference by boron, dividing the obtained difference by a reference value of the basic content of boron 10 and a change factor of the boron 10, and obtaining the distribution condition of the axial boron 10;
a distribution slope calculation module configured to: based on the distribution condition of the axial boron 10, the axial distribution slope of the boron 10 is obtained by adopting a least square method.
The operation method of the system is the same as the method for detecting the coating distribution of the fuel rods boron 10 in the pressurized water reactor nuclear power plant in embodiment 1, and will not be described here again.
Example 4:
the present embodiment provides a computer-readable storage medium having stored thereon a computer program which, when executed by a processor, implements the steps of the pressurized water reactor nuclear power plant fuel rod boron 10 coating distribution detection method described in embodiment 1.
Example 5:
the embodiment provides an electronic device, which comprises a memory, a processor and a computer program stored on the memory and capable of running on the processor, wherein the steps of the method for detecting the coating distribution of the fuel rods and boron 10 in the pressurized water reactor nuclear power plant in embodiment 1 are realized when the processor executes the program.
The above description is only a preferred embodiment of the present embodiment, and is not intended to limit the present embodiment, and various modifications and variations can be made to the present embodiment by those skilled in the art. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present embodiment should be included in the protection scope of the present embodiment.
Claims (10)
1. The method for detecting the coating distribution of the fuel rod boron 10 of the pressurized water reactor nuclear power plant is characterized by comprising the following steps of:
acquiring detection data;
carrying out non-uniformity elimination on the detection data to obtain the count of each counting point of an ideal scanning shape, the count of each counting point of a plurality of batches of average rods and a reference value of the base content of boron 10;
calculating the difference between the count of each counting point of the ideal scanning shape and the count of each counting point of the average rod of a plurality of batches, and dividing the obtained difference by the reference value of the basic content of the boron 10 and the change factor of the boron 10 to obtain the distribution condition of the axial boron 10;
based on the distribution condition of the axial boron 10, the axial distribution slope of the boron 10 is obtained by adopting a least square method.
2. The method for detecting the coating distribution of the fuel rods 10 of the pressurized water reactor nuclear power plant according to claim 1, wherein the bottom low enrichment area of each fuel rod is selected; searching a point with the minimum counting change rate in the low enrichment region by using a least square method; the point with the minimum counting change rate is used as a normalized reference value after being averaged with the adjacent points on the two sides of the point; dividing all the counts of the fuel rods by the reference value to obtain the counts of each counting point of the ideal scanning shape.
3. The method for detecting the boron 10 coating distribution of fuel rods in a pressurized water reactor nuclear power plant according to claim 1, wherein the counts at the same counting points of the fuel rods in each batch are homogenized, and the counts of each counting point of the average rods in a plurality of batches are obtained.
4. A method for detecting the boron 10 coating distribution of a fuel rod in a pressurized water reactor nuclear power plant according to claim 3, wherein the average count of the average rod obtained by averaging the data obtained by cutting off the distances affected by the transition periods at the two ends of the axial boron-coated region is obtained by averaging the data obtained by cutting off the distances affected by the transition periods at the two ends of the axial boron-coated region.
5. The method for detecting the coating distribution of the fuel rods and the boron 10 in the pressurized water reactor nuclear power plant according to claim 4, wherein after the axial boron 10 distribution is obtained, the boron 10 distribution between the distance points of the two ends of the axial boron coating area, which are influenced by the transition period, and the distance points of the two ends, which are influenced by the transition period, is calculated by using a least square method, and the boron 10 distribution in the area influenced by the transition period is extrapolated.
6. The method for detecting the coating distribution of the fuel rods 10 of the pressurized water reactor nuclear power plant according to claim 1, wherein the change factor of the boron 10 refers to the change degree of the front-back counting of the axial boron-coated fuel rods of the enrichment degree.
7. The method for detecting the coating distribution of the fuel rods and the boron 10 in the pressurized water reactor nuclear power plant according to claim 1, wherein the axial distribution slope of the boron 10 is calculated by a least square method based on the axial boron 10 distribution condition:
wherein Bslope is the slope of the boron 10 axial distribution; n is the total count point; b (B) dis Distributed for axial boron 10; mesh is the interval between counting points; i is the number of the count point.
8. A pressurized water reactor nuclear power plant fuel rod boron 10 coating distribution detection system, comprising:
a data acquisition module configured to: acquiring detection data;
a non-uniformity elimination module configured to: carrying out non-uniformity elimination on the detection data to obtain the count of each counting point of an ideal scanning shape, the count of each counting point of a plurality of batches of average rods and a reference value of the base content of boron 10;
calculating the difference between the count of each counting point of the ideal scanning shape and the count of each counting point of the average rod of a plurality of batches, and dividing the obtained difference by the reference value of the basic content of the boron 10 and the change factor of the boron 10 to obtain the distribution condition of the axial boron 10;
a distribution slope calculation module configured to: based on the distribution condition of the axial boron 10, the axial distribution slope of the boron 10 is obtained by adopting a least square method.
9. A computer readable storage medium having stored thereon a computer program, which when executed by a processor, implements the steps of the pressurized water reactor nuclear power plant fuel rod boron 10 coating distribution detection method of any one of claims 1-7.
10. An electronic device comprising a memory, a processor and a computer program stored on the memory and executable on the processor, wherein the processor, when executing the program, implements the steps of the method for detecting the boron 10 coating distribution of a fuel rod of a pressurized water reactor nuclear power plant as defined in any one of claims 1-7.
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