CN117198572B - Nuclear fuel cladding damage online monitoring method based on POD and neutron detection data - Google Patents
Nuclear fuel cladding damage online monitoring method based on POD and neutron detection data Download PDFInfo
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- 238000005253 cladding Methods 0.000 title claims abstract description 111
- 238000001514 detection method Methods 0.000 title claims abstract description 75
- 238000000034 method Methods 0.000 title claims abstract description 41
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 38
- 238000012544 monitoring process Methods 0.000 title claims abstract description 32
- 238000000354 decomposition reaction Methods 0.000 claims abstract description 73
- 238000013507 mapping Methods 0.000 claims abstract description 13
- 238000004088 simulation Methods 0.000 claims abstract description 11
- 239000002826 coolant Substances 0.000 claims abstract description 10
- 239000011159 matrix material Substances 0.000 claims description 38
- 238000010168 coupling process Methods 0.000 claims description 9
- 230000008878 coupling Effects 0.000 claims description 7
- 238000005859 coupling reaction Methods 0.000 claims description 7
- 239000013598 vector Substances 0.000 claims description 6
- 230000008569 process Effects 0.000 claims description 4
- 229910052724 xenon Inorganic materials 0.000 claims description 3
- FHNFHKCVQCLJFQ-UHFFFAOYSA-N xenon atom Chemical compound [Xe] FHNFHKCVQCLJFQ-UHFFFAOYSA-N 0.000 claims description 3
- 238000005070 sampling Methods 0.000 abstract description 6
- 230000002285 radioactive effect Effects 0.000 abstract description 3
- 238000004364 calculation method Methods 0.000 description 4
- 230000000694 effects Effects 0.000 description 4
- 230000006872 improvement Effects 0.000 description 2
- 230000003111 delayed effect Effects 0.000 description 1
- 238000000691 measurement method Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000012847 principal component analysis method Methods 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
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Abstract
The invention discloses a nuclear fuel cladding damage on-line monitoring method based on POD and neutron detection data, which is based on cladding damage state parameter combination of each sampleμAnd the corresponding intrinsic orthogonal decomposition modal coefficienta i (μ) Constructing a mapping relation between the shell damage state parameters and different-order intrinsic orthogonal basis functions so as to lead any intrinsic orthogonal decomposition modal coefficient to bea i (μ) All can uniquely determine a combination of parameters of the damage state of the cladding; according to intrinsic orthogonal decomposition modal coefficientsam i And corresponding combination of parameters of the state of damage of the claddingμThe mapping relation between the two components reversely determines the damage condition of the cladding; the reactor core running state information can be obtained on line in real time through the neutron detector, the detection is quicker and more accurate, and the sampling danger of the radioactive coolant by the traditional detection method is avoided; meanwhile, by combining the POD method, the numerical simulation calculated amount of the whole reactor core prediction can be reduced by more than 4-5 orders of magnitude, the calculated time is reduced to 0.1-ms order, and no hysteresis exists in time.
Description
Technical Field
The invention relates to the field of safety monitoring methods of nuclear fuels of nuclear power plants, in particular to an online monitoring method for damage of a nuclear fuel cladding based on POD and neutron detection data.
Background
On-line monitoring of nuclear fuel cladding damage is important to timely find the safety problem of a nuclear reactor and ensure safe and stable operation of a nuclear power system; the current representative monitoring means for the damage of the nuclear fuel cladding are as follows: ultrasonic detection methods, appearance detection methods, eddy current detection methods, and radioactive product activity measurement methods.
The first three methods can be generally used in the shutdown unloading stage, so that the detection difficulty is high, the interval time is long, and the damage state of the cladding is difficult to discover in time; the radioactivity product activity measuring method mainly obtains radioactivity of coolant in the reactor core through manual sampling and detector sampling methods, and determines the damage state of the cladding by combining physical and empirical model parameters, so that the manual sampling interval time is long, and the radioactivity product activity measuring method has a certain danger to sampling personnel.
In addition, the radioactivity data detected by the radioactivity product activity-based detection method is delayed in time from the damage condition of the cladding, and real-time monitoring is difficult to achieve, so that the real-time and accurate detection of the damage state of the cladding cannot be achieved by the current detection methods.
Disclosure of Invention
In order to solve the technical problems, the invention provides the nuclear fuel cladding damage on-line monitoring method based on POD and neutron detection data, which can rapidly, accurately detect the cladding damage state in real time, and is safer and more reliable.
The technical scheme of the invention is as follows: the nuclear fuel cladding damage on-line monitoring method based on POD and neutron detection data comprises five steps of an off-line stage and two steps of an on-line stage;
step S210, combining a plurality of different cladding breakage status parameters given core coolant inlet conditions and core power levelμUnder the condition of (1) respectively calculating a nuclear-thermal-flow coupling process to obtain neutron distribution sample data of the reactor core in different cladding damage states; multiple different combinations of enclosure breakage state parametersμFrom different positions of shell breakageSNumber of damaged claddingNAnd the size of the opening of the claddingXComposition;
step S220, constructing neutron distribution detection sample databases under different cladding damage conditions according to arrangement conditions of core neutron detectors;
s230, carrying out eigen orthogonal decomposition on the neutron distribution detection sample database to obtain an eigen orthogonal basis function and a characteristic value of a detection neutron field, and extracting a front eigen orthogonal decomposition modal matrix after determining the eigen orthogonal decomposition orderPColumn, reconstruct and detect neutron distribution intrinsic orthomode matrix;
step S240, for each cladding damage condition detection neutron field, dividing the detection neutron field intrinsic orthogonal basis function by the sub-distribution detection sample to obtain intrinsic orthogonal decomposition mode coefficients corresponding to different cladding damage conditionsa i (μ)；
Step S250, combination of parameters of the damage state of the cladding based on each sampleμAnd the corresponding intrinsic orthogonal decomposition modal coefficienta i (μ) Constructing parameters of shell damage state and different-order intrinsic orthogonal decomposition modal coefficientsa i (μ) Mapping relation between the two to make any eigenvalue orthogonal decomposition modal coefficienta i (μ) All can uniquely determine a combination of parameters of the damage state of the cladding;
step S260, dividing the neutron distribution data obtained by detection by the intrinsic orthogonal basis function of the detected neutron field to obtain the intrinsic orthogonal decomposition modal coefficient of the condition to be detectedam i ；
Step S270, according to the intrinsic orthogonal decomposition modal coefficientam i And corresponding combination of parameters of the state of damage of the claddingμAnd the mapping relation between the two components is used for reversely determining the damage condition of the cladding.
The method for monitoring the damage of the nuclear fuel cladding on line based on the POD and the neutron detection data, wherein the step S210 specifically comprises the following steps:
step S212, according to the core condition to be measured,under the normal operation condition of the reactor core, selecting the combination of parameters of the damaged state of the claddingμFor each cladding damage parameterS、NAndX) Within the engineering scope selectN i The number of status points is one,irepresent the firstiA state of damage to the individual clad;
step S214, damaging parameters of different claddingS、NAndX) Combining, and determining the combination of the state parameters of the sample under the damage condition of the claddingμ(S、N、X) Is common toN S ×N N ×N X Sample state parameter combination of the seed shell damage condition;
step S216, under the sample state parameter of each cladding damage condition, carrying out full core nuclear-thermal-flow coupling simulation to calculate neutron distribution under different cladding damage conditionsϕ g =ϕ g (x,y,z|μ) Is a sample of the analog sample data.
The method for monitoring the damage of the nuclear fuel cladding on line based on the POD and the neutron detection data, wherein the step S212 comprises the following steps under the normal operation condition of the reactor core: coolant inlet flow, inlet temperature, power level, average burnup depth, xenon concentration, and control rod position for normal operation.
The method for monitoring the damage of the nuclear fuel cladding based on the POD and the neutron detection data on line, wherein the step S216 further comprises the steps of calculating the damage conditions of different cladding: power distributionP=P(x,y,z|μ) Velocity profileu=u(x,y,z|μ) Distribution of pressurep=p(x,y,z|μ) And temperature distributionT=T(x,y,z|μ) Is a sample of the analog sample data; the energy group division of neutron transport simulation is defined according to the energy range of a neutron detector in the reactor core.
The method for monitoring the damage of the nuclear fuel cladding on line based on the POD and the neutron detection data comprises the following steps when a neutron distribution detection sample database is constructed in step S220Position and energy distribution of partial neutron detector, extracting neutron distribution sample data of detector position from core nuclear-thermal-flow coupling simulation sample data, and forming a new neutron distribution sample matrix of detectorThe neutron distribution sample matrix of the detector is oneN m ×N g The number of rows of the device is,N S ×N N ×N X a matrix of columns is provided which,N m is a positive integer representing the number of detectors;N g the energy group number detected by the detector is represented; if only one energy range is detected, thenN g =1。
The method for monitoring the damage of the nuclear fuel cladding based on the POD and the neutron detection data on line, wherein the step S230 specifically comprises the following steps:
s232, carrying out eigen orthogonal decomposition on neutron distribution sample matrix of the detector to obtainN m ×N g Row of linesN S ×N N ×N X An eigen-orthogonal decomposition mode matrix of columns, each column of the eigen-orthogonal decomposition mode matrix representing one eigen-orthogonal decomposition mode of the detected neutron distribution; at the same time obtainN S ×N N ×N X Eigenvalues of an array from large to smallλ i Each eigenvalue of an eigen-orthogonal decompositionλ i One-to-one correspondence with the intrinsic orthogonal decomposition modes;
step S234, all eigenvalues of the eigenvalue of the eigenvectorλ i Summing to obtain total eigenvalue of orthogonal decompositionλ tot Then, starting from the first eigenvalue, gradually calculating the ratio of the sum of the first eigenvalues to the total eigenvalue and the ratio of the sum of the first eigenvalues to the total eigenvalue is greater than the truncation errorεOrder of timePAs a book required for the cutting accuracyCharacterizing an orthogonal decomposition order;
step S236, extracting the front of the intrinsic orthogonal decomposition modal matrixPAnd (5) reconstructing an intrinsic orthonormal mode matrix of the neutron distribution.
In the method for monitoring the damage of the nuclear fuel cladding based on the POD and the neutron detection data on line, in the step S240, each column of the neutron distribution sample matrix of the detector constructed in the step S220 is used for dividing the detection neutron distribution intrinsic orthomode matrix to obtain a state parameter combination of each cladding damage condition sampleμ(S、N、X) Lower set of eigenvalues of orthogonal decomposition modes corresponding to neutron distribution samples of the detectora i (μ)。
The method for monitoring the damage of the nuclear fuel cladding on line based on the POD and the neutron detection data, wherein the step S260 specifically comprises the following steps:
step S262, during the core operation process, the neutron distribution information detected by the detector is assembled intoN m ×N g Column vectors of rows;
step S264, assembling with a detection signalN m ×N g Dividing the matrix of eigenvalues of neutron distribution of the detector by the row and column vectors to obtain a set of eigenvalues of decomposition corresponding to the current detector signalam i 。
The method for monitoring the damage of the nuclear fuel cladding on line based on the POD and the neutron detection data, wherein the step S270 specifically comprises the following steps:
step S272, intrinsic orthogonal decomposition modal coefficient constructed by step S240a i (μ) And combination of shell breakage state parametersμMapping relation between the two signals, and obtaining the modal coefficient of the signal of the detector by reverse interpolationam i Corresponding parameters of the state of damage of the claddingμ m ；
Step S274 based on the enclosure breakage status parametersμ m Corresponding position of shell breakageSNumber of damaged claddingNAnd the size of the opening of the claddingXThe current core nuclear fuel cladding breakage condition is determined.
According to the nuclear fuel cladding damage on-line monitoring method based on POD and neutron detection data, the nuclear fuel cladding damage on-line monitoring is carried out based on the neutron detection signals, the reactor core running state information can be obtained on line in real time through the neutron detector, the detection is quicker and more accurate, and the sampling danger of the traditional detection method on radioactive coolant is avoided; meanwhile, by combining an intrinsic orthogonal decomposition method, the numerical simulation calculated amount of the whole reactor core prediction can be reduced by more than 4-5 orders of magnitude, and the calculation time is reduced to 0.1-ms order, so that a large amount of calculation resources are saved, the calculation time is greatly shortened, and no hysteresis exists in time.
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The drawings described herein are for illustration purposes only and are not intended to limit the scope of the present disclosure in any way; the shapes and proportional sizes of the components in the drawings are only illustrative, and are not intended to limit the shapes and proportional sizes of the components of the present invention in particular, so as to assist in understanding the present invention; those skilled in the art with access to the teachings of the present invention can select a variety of possible shapes and scale sizes to practice the present invention as the case may be.
FIG. 1 is a flow chart of an embodiment of the nuclear fuel clad breakage on-line monitoring method based on POD and neutron detection data of the present invention.
Description of the embodiments
The following detailed description and examples of the invention are presented in conjunction with the drawings, and the described examples are intended to illustrate the invention and not to limit the invention to the specific embodiments.
As shown in FIG. 1, the nuclear fuel cladding damage on-line monitoring method based on POD and neutron detection data comprises an off-line stage and an on-line stage, and comprises the following steps:
step S210, offline stage, combining at a plurality of different cladding breakage status parameters given core coolant inlet conditions and core power levelμUnder the condition of respectively calculating the core-heat-flow coupling processNeutron distribution sample data of the reactor core in different cladding damage states are obtained; multiple different combinations of enclosure breakage state parametersμFrom different positions of shell breakageSNumber of damaged claddingNAnd the size of the opening of the claddingXComposition;
step S220, constructing neutron distribution detection sample databases under different cladding damage conditions according to arrangement conditions of core neutron detectors;
s230, carrying out eigen orthogonal decomposition on the neutron distribution detection sample database to obtain an eigen orthogonal basis function and a characteristic value of a detection neutron field, and extracting a front eigen orthogonal decomposition modal matrix after determining the eigen orthogonal decomposition orderPColumn, reconstruct and detect neutron distribution intrinsic orthomode matrix;
step S240, for each cladding damage condition detection neutron field, dividing the detection neutron field intrinsic orthogonal basis function by the sub-distribution detection sample to obtain intrinsic orthogonal decomposition mode coefficients corresponding to different cladding damage conditionsa i (μ)；
Step S250, combination of parameters of the damage state of the cladding based on each sampleμAnd the corresponding intrinsic orthogonal decomposition modal coefficienta i (μ) Constructing parameters of shell damage state and different-order intrinsic orthogonal decomposition modal coefficientsa i (μ) Mapping relation between the two to make any eigenvalue orthogonal decomposition modal coefficienta i (μ) All can uniquely determine a combination of parameters of the damage state of the cladding;
step S260, in the online stage, dividing the neutron distribution data obtained by detection by the intrinsic orthogonal basis function of the neutron field to obtain the intrinsic orthogonal decomposition modal coefficient of the condition to be detectedam i ；
Step S270, according to the intrinsic orthogonal decomposition modal coefficientam i And corresponding combination of parameters of the state of damage of the claddingμAnd the mapping relation between the two components is used for reversely determining the damage condition of the cladding.
In detail, the step S210 specifically includes:
step S212, selecting a combination of parameters of the damaged state of the cladding under the normal operation condition of the reactor core (including the coolant inlet flow, inlet temperature, power level, average burnup depth, xenon concentration and control rod position of normal operation) according to the reactor core condition to be measuredμIs included in the range of (including different positions of shell breakageSNumber of damaged claddingNAnd the size of the opening of the claddingX) For each cladding damage parameterS、NAndX) Within the engineering scope selectN i The number of status points is one,irepresent the firstiA state of damage to the individual clad;
step S214, damaging parameters of different claddingS、NAndX) Combining, and determining the combination of the state parameters of the sample under the damage condition of the claddingμ(S、N、X) Is common toN S ×N N ×N X Sample state parameter combination of the seed shell damage condition;
step S216, under the sample state parameter of each cladding damage condition, carrying out full core nuclear-thermal-flow coupling simulation to calculate neutron distribution under different cladding damage conditionsϕ g =ϕ g (x,y,z|μ) Power distributionP=P(x,y,z|μ) Velocity profileu=u(x,y,z|μ) Distribution of pressurep=p(x,y,z|μ) And temperature distributionT=T(x,y,z|μ) Wherein the energy swarm division of the neutron transport simulation is defined in terms of the energy range of the neutron detector inside the core.
In detail, in the step S220: extracting neutron distribution sample data of the detector position from the whole reactor core nuclear-thermal-flow coupling simulation sample data according to the position and energy distribution of the neutron detector in the reactor core to form a new neutron distribution sample matrix of the detectorThe neutron distribution sample matrix of the detector is oneN m ×N g The number of rows of the device is,N S ×N N ×N X a matrix of columns is provided which,N m is a positive integer representing the number of detectors;N g the energy group number detected by the detector is represented; if only one energy range is detected, thenN g =1。
In detail, the step S230 specifically includes:
s232, carrying out eigen orthogonal decomposition on the neutron distribution sample matrix of the detector constructed in the step S220 to obtainN m ×N g Row of linesN S ×N N ×N X An eigen-orthogonal decomposition mode matrix of columns, each column of the eigen-orthogonal decomposition mode matrix representing one eigen-orthogonal decomposition mode of the detected neutron distribution; at the same time obtainN S ×N N ×N X Eigenvalues of an array from large to smallλ i Each eigenvalue of an eigen-orthogonal decompositionλ i One-to-one correspondence with the intrinsic orthogonal decomposition modes;
step S234, all eigenvalues of the eigenvalue of the eigenvectorλ i Summing to obtain total eigenvalue of orthogonal decompositionλ tot Then, starting from the first eigenvalue, gradually calculating the ratio of the sum of the first eigenvalues to the total eigenvalue and the ratio of the sum of the first eigenvalues to the total eigenvalue is greater than the truncation errorεOrder of timePAn intrinsic orthogonal decomposition order required for the truncation accuracy;
step S236, extracting the front of the intrinsic orthogonal decomposition modal matrixPAnd (5) reconstructing an intrinsic orthonormal mode matrix of the neutron distribution.
In detail, in the step S240: dividing each column of the neutron distribution sample matrix of the detector constructed in the step S220 by the detection neutron distribution eigen-orthonormal mode matrix to obtain the state of each cladding damage condition sampleParameter combinationμ(S、N、X) Lower set of eigenvalues of orthogonal decomposition modes corresponding to neutron distribution samples of the detectora i (μ) 。
In detail, the step S260 specifically includes:
step S262, during the core operation process, the neutron distribution information detected by the detector is assembled intoN m ×N g Column vectors of rows;
step S264, assembling with a detection signalN m ×N g Dividing the matrix of eigenvalues of neutron distribution of the detector by the row and column vectors to obtain a set of eigenvalues of decomposition corresponding to the current detector signalam i 。
In detail, the step S270 specifically includes:
step S272, intrinsic orthogonal decomposition modal coefficient constructed by step S240a i (μ) And combination of shell breakage state parametersμMapping relation between the two signals, and obtaining the modal coefficient of the signal of the detector by reverse interpolationam i Corresponding parameters of the state of damage of the claddingμ m ；
Step S274 based on the enclosure breakage status parametersμ m Corresponding position of shell breakageSNumber of damaged claddingNAnd the size of the opening of the claddingX) The current core nuclear fuel cladding breakage condition is determined.
According to the nuclear fuel cladding damage on-line monitoring method based on the intrinsic orthogonal decomposition (POD) and neutron detection data, neutron distribution (including neutron distribution at detection points) in different nuclear fuel cladding damage states is taken as an intrinsic orthogonal decomposition sample, a mapping relation between neutron distribution intrinsic orthogonal decomposition coefficients and cladding damage states is constructed, the damage state of the nuclear fuel cladding is rapidly and accurately determined under the condition of neutron detection data, and the problems of time lag and inaccurate detection of the existing nuclear fuel cladding damage detection means are solved; in particular, in step S250, how to establish the mapping relationship between the neutron distribution POD coefficient and the damaged state of the cladding, and in combination with the reverse determination in step S270, no related technical means are disclosed or reported in the prior art.
The nuclear fuel cladding damage on-line monitoring method based on POD and neutron detection data has good use experience through simulating and checking a certain pile type reference problem and verifying a calculation process and a detection result, does not realize simple functions in complex steps or combine or stack by adopting conventional or simple characteristics, accords with the ordinary principle of technical improvement, and has practicability.
What is not described in detail in this specification is all that is known to those of ordinary skill in the art.
It should be understood that the foregoing description is only a preferred embodiment of the present invention, and is not intended to limit the technical solution of the present invention, and it is within the spirit and principles of the present invention to add, replace, transform or modify the present invention according to the foregoing description, for example, the intrinsic orthogonal decomposition method may be replaced by other various dimension-reducing decomposition methods, including dynamic modal decomposition methods, principal component analysis methods, etc.; for another example, the detection signals such as temperature and pressure can be used as detection information to determine the damage state of the nuclear fuel; for another example, more status information, such as coolant inlet flow, inlet temperature, etc., may be added to the status parameters; all such modifications, substitutions, variations and improvements are intended to be within the scope of the following claims.
Claims (8)
1. The nuclear fuel cladding damage on-line monitoring method based on POD and neutron detection data is characterized by comprising five steps in an off-line stage and two steps in an on-line stage;
step S210, combining a plurality of different cladding breakage status parameters given core coolant inlet conditions and core power levelμUnder the condition of (1) respectively calculating a nuclear-thermal-flow coupling process to obtain neutron distribution sample data of the reactor core in different cladding damage states; multiple does notSame combination of parameters of shell breakageμFrom different positions of shell breakageSNumber of damaged claddingNAnd the size of the opening of the claddingXComposition;
step S220, constructing neutron distribution detection sample databases under different cladding damage conditions according to arrangement conditions of core neutron detectors;
s230, carrying out eigen orthogonal decomposition on the neutron distribution detection sample database to obtain an eigen orthogonal basis function and a characteristic value of a detection neutron field, and extracting a front eigen orthogonal decomposition modal matrix after determining the eigen orthogonal decomposition orderPColumn, reconstruct and detect neutron distribution intrinsic orthomode matrix;
step S240, for each cladding damage condition detection neutron field, dividing the detection neutron field intrinsic orthogonal basis function by the sub-distribution detection sample to obtain intrinsic orthogonal decomposition mode coefficients corresponding to different cladding damage conditionsa i (μ)；
Step S250, combination of parameters of the damage state of the cladding based on each sampleμAnd the corresponding intrinsic orthogonal decomposition modal coefficienta i (μ) Constructing parameters of shell damage state and different-order intrinsic orthogonal decomposition modal coefficientsa i (μ) Mapping relation between the two to make any eigenvalue orthogonal decomposition modal coefficienta i (μ) All can uniquely determine a combination of parameters of the damage state of the cladding;
step S260, dividing the neutron distribution data obtained by detection by the intrinsic orthogonal basis function of the detected neutron field to obtain the intrinsic orthogonal decomposition modal coefficient of the condition to be detectedam i ；
Step S270, according to the intrinsic orthogonal decomposition modal coefficientam i And corresponding combination of parameters of the state of damage of the claddingμThe mapping relation between the two components reversely determines the damage condition of the cladding; the step S270 specifically includes:
step S272, intrinsic orthogonal decomposition modal coefficient constructed by step S240a i (μ) And combination of shell breakage state parametersμMapping relation between the two signals, and obtaining the modal coefficient of the signal of the detector by reverse interpolationam i Corresponding parameters of the state of damage of the claddingμ m ；
Step S274 based on the enclosure breakage status parametersμ m Corresponding position of shell breakageSNumber of damaged claddingNAnd the size of the opening of the claddingXThe current core nuclear fuel cladding breakage condition is determined.
2. The method for on-line monitoring of nuclear fuel cladding damage based on POD and neutron detection data according to claim 1, wherein the step S210 specifically comprises:
step S212, selecting a combination of parameters of the damaged state of the cladding under the normal operation condition of the reactor core according to the reactor core condition to be measuredμFor each cladding damage parameterS、NAndX) Within the engineering scope selectN i The number of status points is one,irepresent the firstiA state of damage to the individual clad;
step S214, damaging parameters of different claddingS、NAndX) Combining, and determining the combination of the state parameters of the sample under the damage condition of the claddingμ(S、N、X) Is common toN S ×N N ×N X Sample state parameter combination of the seed shell damage condition;
step S216, under the sample state parameter of each cladding damage condition, carrying out full core nuclear-thermal-flow coupling simulation to calculate neutron distribution under different cladding damage conditionsϕ g =ϕ g (x, y, z | μ) Is a sample of the analog sample data.
3. The method for on-line monitoring of nuclear fuel cladding damage based on POD and neutron detection data according to claim 2, wherein step S212 comprises, under core normal operation conditions: coolant inlet flow, inlet temperature, power level, average burnup depth, xenon concentration, and control rod position for normal operation.
4. The method for on-line monitoring of nuclear fuel clad damage based on POD and neutron detection data according to claim 2, wherein step S216 further comprises calculating the following conditions of different clad damage: power distributionP=P (x, y, z| μ) Velocity profileu=u (x, y, z | μ) Distribution of pressurep=p (x, y, z | μ) And temperature distributionT=T (x, y, z | μ) Is a sample of the analog sample data; the energy group division of neutron transport simulation is defined according to the energy range of a neutron detector in the reactor core.
5. The on-line monitoring method for nuclear fuel cladding damage based on POD and neutron detection data of claim 1, wherein: in the step S220, when a neutron distribution detection sample database is constructed, neutron distribution sample data of the detector position is extracted from the whole reactor core nuclear-thermal-flow coupling simulation sample data according to the position and the energy distribution of the neutron detector in the reactor core to form a new neutron distribution sample matrix of the detectorThe neutron distribution sample matrix of the detector is oneN m ×N g The number of rows of the device is,N S ×N N ×N X a matrix of columns is provided which,N m is a positive integer representing the number of detectors;N g the energy group number detected by the detector is represented; if only one energy range is detected, thenN g =1。
6. The method for on-line monitoring of nuclear fuel cladding damage based on POD and neutron detection data according to claim 5, wherein the step S230 specifically comprises:
step S232, for neutron distribution sample of detectorMatrix, carrying out eigen orthogonal decomposition to obtainN m ×N g Row of linesN S ×N N ×N X An eigen-orthogonal decomposition mode matrix of columns, each column of the eigen-orthogonal decomposition mode matrix representing one eigen-orthogonal decomposition mode of the detected neutron distribution; at the same time obtainN S ×N N ×N X Eigenvalues of an array from large to smallλ i Each eigenvalue of an eigen-orthogonal decompositionλ i One-to-one correspondence with the intrinsic orthogonal decomposition modes;
step S234, all eigenvalues of the eigenvalue of the eigenvectorλ i Summing to obtain total eigenvalue of orthogonal decompositionλ tot Then, starting from the first eigenvalue, gradually calculating the ratio of the sum of the first eigenvalues to the total eigenvalue and the ratio of the sum of the first eigenvalues to the total eigenvalue is greater than the truncation errorεOrder of timePAn intrinsic orthogonal decomposition order required for the truncation accuracy;
step S236, extracting the front of the intrinsic orthogonal decomposition modal matrixPAnd (5) reconstructing an intrinsic orthonormal mode matrix of the neutron distribution.
7. The on-line monitoring method for nuclear fuel cladding damage based on POD and neutron detection data of claim 5, wherein: step S240 is to divide each column of the neutron distribution sample matrix of the detector constructed in step S220 by the detection neutron distribution eigen-orthonormal mode matrix to obtain a sample state parameter combination of each cladding damage conditionμ(S、N、X) Lower set of eigenvalues of orthogonal decomposition modes corresponding to neutron distribution samples of the detectora i (μ)。
8. The method for on-line monitoring of nuclear fuel cladding damage based on POD and neutron detection data according to claim 1, wherein the step S260 specifically comprises:
step S262, during the core operation process, the neutron distribution information detected by the detector is assembled intoN m ×N g Column vectors of rows;
step S264, assembling with a detection signalN m ×N g Dividing the matrix of eigenvalues of neutron distribution of the detector by the row and column vectors to obtain a set of eigenvalues of decomposition corresponding to the current detector signalam i 。
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