CN111797509B - Reactor core neutron flux prediction method based on detector measurement value - Google Patents

Reactor core neutron flux prediction method based on detector measurement value Download PDF

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CN111797509B
CN111797509B CN202010543625.8A CN202010543625A CN111797509B CN 111797509 B CN111797509 B CN 111797509B CN 202010543625 A CN202010543625 A CN 202010543625A CN 111797509 B CN111797509 B CN 111797509B
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李茁
马宇
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Sun Yat Sen University
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Abstract

The invention discloses a reactor core neutron flux prediction method based on detector measured values, which comprises the steps of reading and recording reactor core detector measured values at different positions of a reactor core from an in-reactor detection system at different time points, fitting the in-reactor detector measured values at past time points and current time points, extrapolating the in-reactor detector measured values, adopting a reactor core fuel management program to simulate and calculate the neutron flux at different time points, carrying out intrinsic orthogonal decomposition, and calculating the reactor core neutron flux predicted value at a future time point; the core algorithm of the original reactor core neutron flux online monitoring system is prevented from being changed by predicting the measured value of the in-reactor detector and combining the online reactor core neutron flux reconstruction method, and the measured value of the in-reactor detector at each position is separately subjected to fitting extrapolation only including one independent variable dimension of time, so that the prediction precision is ensured, the overall failure of prediction calculation caused by failure of individual or local detectors is reduced, and the accurate prediction of the reactor core neutron flux is realized.

Description

Reactor core neutron flux prediction method based on detector measurement value
Technical Field
The invention relates to the field of prediction means of neutron flux of a nuclear reactor core of a power plant, in particular to a method for predicting the neutron flux of the reactor core based on a detector measurement value.
Background
The function and action of the on-line monitoring system for the power distribution of the reactor core of the nuclear reactor of the power plant, also called the on-line monitoring system for the neutron flux of the reactor core, include four aspects, namely tracking, monitoring, forecasting and alarming, so as to realize the full utilization of the existing equipment in the on-line monitoring system for the neutron flux of the reactor core, and have important significance for ensuring the operation and safety of the reactor core and improving the economic benefit of the nuclear power plant.
In order to realize on-line monitoring of neutron flux in a nuclear reactor core, an in-core neutron detector and a signal processor, a central processing unit and various data and signal transmission wires which are additionally installed in the nuclear reactor are required, and both the cost of the elements and the design and maintenance cost of the reactor caused by the installation of the elements, such as the shielding cost caused by the opening of the originally sealed wall surface, including an on-line monitoring calculation algorithm, can cause the increase of the construction and operation cost of a nuclear power plant.
At present, the nuclear reactor core tracking calculation and the neutron flux online monitoring calculation are fully researched at home and abroad in China, for example, the nuclear reactor core tracking calculation function based on a fuel management program and the online monitoring realized by using the reactor core neutron flux online reconstruction method are adopted.
The common nuclear reactor core neutron flux online reconstruction method comprises the following steps: harmonic synthesis, spline function fitting, coupling coefficient, least square, polynomial expansion, internal boundary condition, error shape synthesis, weight factor, general Kriging and intrinsic orthogonal decomposition.
However, research on prediction of neutron flux in a nuclear reactor core is few, and reports on alarm of the state of the nuclear reactor core are rare; the biggest difference between the in-core neutron flux prediction calculation and the in-core neutron flux on-line monitoring calculation is that the in-core neutron flux prediction calculation of the nuclear reactor is a calculation comprising a time dimension and is characterized by a time variable, if the existing in-core neutron flux on-line reconstruction method is considered to be used in the prediction calculation, the time variable cannot be introduced by other calculation methods except for a harmonic synthesis method and an intrinsic orthogonal decomposition method based on a function expansion idea, and the core algorithm of the early-developed in-core neutron flux on-line monitoring system is determined, so that the change algorithm does not accord with the original purpose of fully utilizing the existing equipment of the system.
Therefore, both from the viewpoint of the development of scientific research and from the viewpoint of engineering application, a suitable and practical method for predicting the neutron flux in the nuclear reactor core needs to be developed.
Disclosure of Invention
In order to solve the technical problems, the invention provides a reactor core neutron flux prediction method based on a detector measured value, which can avoid changing the core algorithm of the original reactor core neutron flux on-line monitoring system and realize accurate prediction of the reactor core neutron flux.
The technical scheme of the invention is as follows: a method for predicting neutron flux in a reactor core based on measured values of a detector comprises the following steps:
A. at the past time point according to the position of each detector in the core
Figure DEST_PATH_IMAGE002
Current point in time
Figure DEST_PATH_IMAGE004
And future point in time
Figure DEST_PATH_IMAGE006
Reading and recording the measured values of the in-core detector at different positions of the reactor core at different time points from the reactor core neutron flux on-line monitoring system
Figure DEST_PATH_IMAGE008
(ii) a Wherein,
Figure DEST_PATH_IMAGE010
which is indicative of the position of the detector within the stack,
Figure DEST_PATH_IMAGE012
，Mthe number of detectors in the stack;
B. taking time as a variable, and converting the past time point
Figure 587721DEST_PATH_IMAGE002
And the current time point
Figure DEST_PATH_IMAGE013
In-core detector measurements at different locations of the core
Figure DEST_PATH_IMAGE015
Fitting to obtain the time-varying function of each in-pile detector measurement value
Figure DEST_PATH_IMAGE017
；
C. As a function of time from in-stack detector measurements
Figure DEST_PATH_IMAGE019
Extrapolating the measured value of the in-pile detector to obtain the future time point
Figure 64226DEST_PATH_IMAGE006
Prediction of in-core detector measurements at different locations in the core
Figure 797827DEST_PATH_IMAGE015
，
Figure 315134DEST_PATH_IMAGE012
；
D. Simulating and calculating neutron flux of different positions of the reactor core at different time points by adopting a reactor core fuel management program
Figure DEST_PATH_IMAGE021
，
Figure DEST_PATH_IMAGE023
，NThe number of time points calculated for the simulation;
E. neutron flux to different locations of the core at different time points
Figure DEST_PATH_IMAGE025
Performing intrinsic orthogonal decomposition to obtain intrinsic orthogonal basis function
Figure DEST_PATH_IMAGE027
；
F. The eigen-orthogonal basis functions
Figure 9551DEST_PATH_IMAGE027
Combining step C future time points
Figure DEST_PATH_IMAGE028
Prediction of in-core detector measurements at different locations in a reactor core
Figure 945540DEST_PATH_IMAGE015
Calculating future time points, respectively
Figure 595964DEST_PATH_IMAGE006
Reactor core neutron flux prediction value of different positions of reactor core
Figure DEST_PATH_IMAGE030
。
The reactor core based on the measured value of the detectorA method of flux prediction, wherein: in step F, the predicted value is determined according to the measured value of the in-pile detector
Figure DEST_PATH_IMAGE032
Calculating reactor core neutron flux predicted value
Figure DEST_PATH_IMAGE034
，
Figure DEST_PATH_IMAGE036
Are coefficients.
The reactor core neutron flux prediction method based on the detector measurement value comprises the following steps: firstly, the coefficient is calculated according to the least square principle
Figure DEST_PATH_IMAGE037
According to the intrinsic orthogonal basis function
Figure DEST_PATH_IMAGE038
Calculating reactor core neutron flux predicted value
Figure 644691DEST_PATH_IMAGE030
。
The reactor core neutron flux prediction method based on the detector measurement value comprises the following steps: in the steps D-F, if the core algorithm of the original reactor core neutron flux on-line monitoring system is a harmonic wave synthesis method or a spline function fitting method, the harmonic wave synthesis method or the spline function fitting method is adopted to replace the intrinsic orthogonal decomposition method.
The reactor core neutron flux prediction method based on the detector measurement value comprises the following steps: in step D, the time points calculated by the simulation include core states for core average burnup, boron concentration, control rod position, and relative power levels.
The reactor core neutron flux prediction method based on the detector measurement value comprises the following steps: in step C, a future time point
Figure 792119DEST_PATH_IMAGE006
The number of (2) to (4).
The reactor core neutron flux prediction method based on the detector measurement value comprises the following steps: in the step B, the fitting method adopts spline function fitting or simple polynomial fitting, and the order of the fitting selects second-order fitting.
The reactor core neutron flux prediction method based on the detector measurement value comprises the following steps: in the step A, determining the past time point according to the sampling time interval of the reactor core neutron flux on-line monitoring system
Figure DEST_PATH_IMAGE039
And future point in time
Figure 499175DEST_PATH_IMAGE006
And only the past time point is reserved
Figure DEST_PATH_IMAGE040
In-core detector measurement values with determined variation trend at different positions of reactor core
Figure 472947DEST_PATH_IMAGE008
。
According to the reactor core neutron flux prediction method based on the detector measured value, the core algorithm of the original reactor core neutron flux online monitoring system is prevented from being changed by predicting the measured value of the in-reactor detector and combining the reactor core neutron flux online reconstruction method, and the in-reactor detector measured value at each position is separately subjected to fitting extrapolation only including one independent variable dimension of time, so that the prediction precision is ensured, the prediction calculation overall failure caused by the failure of an individual or local detector is reduced, and the accurate prediction of the reactor core neutron flux is realized.
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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, the proportional sizes, and the like of the respective members in the drawings are merely schematic for aiding the understanding of the present invention, and do not specifically limit the shapes, the proportional sizes, and the like of the respective members of the present invention; those skilled in the art, having the benefit of the teachings of this invention, may choose from the various possible shapes and proportional sizes to implement the invention as a matter of case.
FIG. 1 is a general flow diagram of a method for detector measurement based in-core neutron flux prediction according to the present invention;
FIG. 2 is a schematic layout of an exemplary PWR core fuel embodiment for use in the method for detector measurement based neutron flux prediction of the present invention;
FIG. 3 is a schematic representation of the time-dependent change in detector measurements within the E09 channel stack of FIG. 2 in accordance with the present invention;
fig. 4 is a graphical representation of the time-dependent detector measurements for the N06 channel stack of fig. 2 in accordance with the present invention.
Detailed Description
The embodiments and examples of the present invention will be described in detail below with reference to the accompanying drawings, and the described embodiments are only for the purpose of illustrating the present invention and are not intended to limit the embodiments of the present invention.
As shown in fig. 1, fig. 1 is a general flowchart of the method for predicting neutron flux in a reactor core based on measured values of a detector, and the method for predicting neutron flux in a reactor core based on measured values of a detector comprises the following steps:
s210, reading and recording in-core detector measurement values at different positions of the reactor core from the reactor core neutron flux online monitoring system at different time points; i.e. recording the past time points of the position of each detector of the core
Figure 4160DEST_PATH_IMAGE002
Current time point
Figure 860121DEST_PATH_IMAGE013
And future point in time
Figure 964343DEST_PATH_IMAGE006
Reading and recording the measured values of the in-core detector at different positions of the reactor core at different time points from the in-core detection system (namely the reactor core neutron flux on-line monitoring system)
Figure DEST_PATH_IMAGE041
(ii) a It is composed ofIn (1),
Figure 995884DEST_PATH_IMAGE010
which is indicative of the position of the detector within the stack,
Figure 261780DEST_PATH_IMAGE012
，Mthe number of detectors in the stack;
step S220, taking time as variable, and taking the past time point recorded in the step S210
Figure 605037DEST_PATH_IMAGE040
In-core detector measurements at different locations of the core
Figure 889781DEST_PATH_IMAGE041
From the current point in time
Figure 634883DEST_PATH_IMAGE004
In-core detector measurements at different locations of the core
Figure 274943DEST_PATH_IMAGE008
Fitting to obtain the time-varying function of each in-pile detector measurement value
Figure DEST_PATH_IMAGE042
；
Step S230, according to the time-varying function of the measured value of the in-pile detector obtained in the step S220
Figure 807293DEST_PATH_IMAGE019
Extrapolating the measured value of the in-pile detector to obtain the future time point
Figure 253318DEST_PATH_IMAGE006
Prediction of in-core detector measurements at different locations in a reactor core
Figure 790610DEST_PATH_IMAGE041
，
Figure 398309DEST_PATH_IMAGE012
；
Step S240, simulating and calculating neutron fluxes of different positions of the reactor core at different time points by adopting a reactor core fuel management program
Figure 716157DEST_PATH_IMAGE021
，
Figure 637977DEST_PATH_IMAGE023
，NNumber of time points calculated for the simulation;
step S250, calculating neutron flux of different positions of the reactor core at different time points in a simulation manner in step S240
Figure 859136DEST_PATH_IMAGE025
Performing intrinsic orthogonal decomposition to obtain intrinsic orthogonal basis function
Figure DEST_PATH_IMAGE043
；
Step S260, the intrinsic orthogonal basis function obtained in the step S250
Figure 44261DEST_PATH_IMAGE038
Combined with the extrapolation of the future time point in step S230
Figure 787089DEST_PATH_IMAGE006
Prediction of in-core detector measurements at different locations in a reactor core
Figure 574917DEST_PATH_IMAGE015
Calculating future time points, respectively
Figure 382073DEST_PATH_IMAGE006
Reactor core neutron flux prediction value of different positions of reactor core
Figure 534837DEST_PATH_IMAGE030
。
Steps S210-S230 in the reactor core neutron flux prediction method based on the measured value of the detector are calculated in real time, and steps S240-S260 are calculated in advance and stored; before neutron flux prediction calculation is carried out, prediction calculation of the measured value of the in-reactor detector is carried out firstly, and then the intrinsic orthogonal decomposition method is combined on the basis, so that accurate prediction of the neutron flux of the reactor core is realized.
Compared with the prior art, the reactor core neutron flux prediction method based on the detector measurement value has the following outstanding advantages:
1) The prediction of the reactor core neutron flux is reflected in the prediction of the measured value of the in-reactor detector, the core algorithm of the reactor core neutron flux on-line monitoring system is not influenced, the upgrading and the transplanting are more convenient, and the method also meets the original purpose of fully utilizing the existing equipment of the system;
2) the measured value of the in-pile detector at each position is subjected to fitting extrapolation and prediction independently, so that the overall failure of prediction calculation caused by failure of individual or local detectors is avoided;
3) the fitting and the extrapolation of the measured values of the in-core detector only comprise one independent variable dimension of time, so that the calculation accuracy of the neutron flux prediction calculation of the reactor core is ensured.
In step S210, the past time point is not specified
Figure 561699DEST_PATH_IMAGE002
Number of and future point in time
Figure 887638DEST_PATH_IMAGE006
The specific number of the active carbon particles can be determined according to the actual application condition; preferably, the past time point is determined according to the actual condition of the sampling time interval of the reactor core neutron flux on-line monitoring system
Figure 254028DEST_PATH_IMAGE002
And future point in time
Figure 374431DEST_PATH_IMAGE006
While only preserving past time points
Figure 655633DEST_PATH_IMAGE040
In-core detector measurement values with determined variation trend at different positions of reactor core
Figure 722946DEST_PATH_IMAGE008
And (4) finishing.
In step S220, the fitting method of the in-pile detector measurement values is not limited, and the fitting method is not limited, but only one time independent variable is provided, spline function fitting or simple polynomial fitting is recommended in consideration of the number of independent variables and the variation range and trend of dependent variables, the fitting order is determined according to the actual application condition, and the accuracy requirement can be met by recommending and selecting second-order fitting.
In step S230, the future time point is not specified either
Figure 740581DEST_PATH_IMAGE006
Extrapolation of future time points, extrapolation of too long a time introducing or causing bias accumulation, but since the acquisition time points of the detector measurements in each stack can be made to be future time points
Figure 297464DEST_PATH_IMAGE006
Thus, recommending a future point in time
Figure 298918DEST_PATH_IMAGE006
The number of (2) to (4) is preferable.
In step S240, although the specific core fuel management program is not limited, the simulation calculation time point recommends a sample selection method in the reactor core neutron flux on-line reconstruction, which includes as many reactor core states as possible, such as average reactor core burnup, boron concentration, control rod position, and relative power level, to improve the prediction accuracy.
In step S260, the predicted value of the in-pile detector measurement value is
Figure DEST_PATH_IMAGE045
Expression, hence prediction from in-stack detector measurements
Figure DEST_PATH_IMAGE046
First, the coefficients are calculated
Figure 543824DEST_PATH_IMAGE036
And then calculating the neutron flux predicted value of the reactor core
Figure 415965DEST_PATH_IMAGE034
(ii) a Preferably, the coefficients are first calculated according to the least squares principle
Figure 409329DEST_PATH_IMAGE036
According to the intrinsic orthogonal basis function
Figure DEST_PATH_IMAGE047
Calculating reactor core neutron flux predicted value
Figure 794349DEST_PATH_IMAGE030
。
In steps S250-S260, if the core algorithm of the original reactor core neutron flux on-line monitoring system is other algorithms such as a harmonic wave synthesis method or a spline function fitting method, the harmonic wave synthesis method or the spline function fitting method is adopted to replace the intrinsic orthogonal decomposition method.
In the preferred embodiment of the reactor core neutron flux prediction method based on the detector measured value, in order to verify the effectiveness of the reactor core neutron flux prediction method based on the detector measured value, the invention adopts a typical pressurized water reactor core design verification example, and because the prediction precision of the reactor core neutron flux depends on the prediction precision of the measured value of the in-reactor detector, the invention only inspects whether the change trend of the measured value of the in-reactor detector along with time is easy to capture and predict.
Referring to FIG. 2, FIG. 2 is a schematic layout of an exemplary PWR core fuel embodiment used in the method for neutron flux prediction based on detector measurements according to the present invention, where the numbers in different squares represent the number of burnable poison rods of different types in the fuel bundle, and 1.6 w/o U-235, 2.4 w/o U-235, and 3.1 w/o U-235 represent the fuel enrichment of the burnable poison rods as 1.6%, 2.4%, and 3.1%, respectively; .
Referring to fig. 3 and 4, fig. 3 is a graph showing the time variation of the detector measurement value in the E09 channel stack of fig. 2 according to the present invention, and fig. 4 is a graph showing the time variation of the detector measurement value in the N06 channel stack of fig. 2 according to the present invention; the horizontal coordinate x is an acquisition time point, the unit is second, and the vertical coordinate y is a measured value of the in-pile detector; as can be seen from fig. 3 and 4, the in-stack detector measurement time-varying curve characteristics of the E09 channel or N06 channel have become easily described within the acquisition time interval on the order of seconds, and a fitting form of a first or second order polynomial is sufficient, and the fitting accuracy is high.
Therefore, the reactor core neutron flux prediction method based on the detector measurement value is applied to reactor core neutron flux prediction calculation, the change of a reactor core neutron flux on-line monitoring system core algorithm is better avoided through the prediction of the in-reactor detector measurement value, the in-reactor detector measurement value at each position is separately subjected to fitting extrapolation only comprising one independent variable dimension of time, the prediction precision is ensured, the whole prediction calculation failure caused by the failure of individual or local detectors is reduced, and the accurate prediction of the reactor core neutron flux is realized.
It should be understood that the above description is only a preferred embodiment of the present invention, and is not meant to limit the technical solutions of the present invention, and it will be apparent to those skilled in the art that the above descriptions may be added, removed, replaced, changed or modified according to the above description within the spirit and principle of the present invention, for example, the steps 240 to 260 of the present invention are described according to the intrinsic orthogonal decomposition method of the reactor core neutron flux online reconstruction method, if the core algorithm of the original reactor core neutron flux online monitoring system is other algorithms such as harmonic synthesis method or spline function fitting method, the steps 240 to 260 may be modified correspondingly, so as to implement convenient transplantation; all the changes, substitutions, transformations, or modifications that fall within the scope of the appended claims should be construed as being included therein.

Claims (7)

1. A reactor core neutron flux prediction method based on detector measurement values is characterized by comprising the following steps:
A. at the past time t according to the position of each detector in the core0，t1，...，ti-2，ti-1Current time point tiAnd a future point in time ti+1，ti+2,., reading and recording the in-core detector measured values d (r) of different positions of the reactor core at different time points from the reactor core neutron flux on-line monitoring systemm，to)，d(rm，t1)，...，d(rm，ti) ,..; wherein r ismRepresenting the position of the in-pile detectors, wherein M is 1, 2, and M is the number of the in-pile detectors;
B. taking time as a variable, and converting the past time point t0，t1，...，ti-2，ti-1And the current time point tiIn-core detector measurements d (r) at different locations of the corem，t0)，d(rm，t1)，...，d(rm，ti) ,.. fitting to obtain a function D (r) of the time variation of each in-pile detector measurement valuem，t)，m＝1，2，...，M；
C. According to the time-varying function D (r) of the in-pile detector measurementmT), extrapolating the measured value of the in-pile detector to obtain a future time point ti+1，ti+2,.. predicted values d (r) of in-core detector measurements at different locations of the corem，ti+1)，d(rm，ti-2)，...，m＝1，2，...，M；
D. Simulating and calculating neutron flux of different positions of reactor core at different time points by adopting reactor core fuel management program
Figure FDA0003587273900000011
c is 1, 2, N is the number of time points of the simulation calculation;
E. neutron flux to different locations of the core at different time points
Figure FDA0003587273900000012
Performing intrinsic orthogonal divisionSolving to obtain an intrinsic orthogonal basis function psin(r)，n＝1，2，...，N；
F. Transforming the intrinsic orthogonal basis function psin(r) combining step C future time points ti+1，ti+2,.. predicted values d (r) of in-core detector measurements at different locations in the corem，ti-1)，d(rm，ti-2) ,.
Figure FDA0003587273900000013
Wherein, x is 1, 2.; first, the coefficient a is calculatednThen according to the intrinsic orthogonal basis function psin(r) and
Figure FDA0003587273900000014
respectively calculating future time points ti+1，ti+2,.. core neutron flux prediction values for different positions of the core
Figure FDA0003587273900000015
2. The detector measurement based in-core neutron flux prediction method of claim 1, characterized by: calculating coefficient a according to the least square principlen。
3. The detector measurement based in-core neutron flux prediction method of claim 1, characterized by: in the steps D-F, if the core algorithm of the original reactor core neutron flux on-line monitoring system is a harmonic wave synthesis method or a spline function fitting method, the harmonic wave synthesis method or the spline function fitting method is adopted to replace the intrinsic orthogonal decomposition method.
4. The detector measurement based in-core neutron flux prediction method of claim 1, characterized by: in step D, the simulated calculated time points include core states of core average burnup, boron concentration, control rod position, relative power levels.
5. The method of detector measurement based prediction of neutron flux in a core of claim 1, wherein: in step C, a future time point ti+1，ti+2,.. the number of the filter paper is 2-4.
6. The method of detector measurement based prediction of neutron flux in a core of claim 1, wherein: in the step B, the fitting method adopts spline function fitting or simple polynomial fitting, and the order of the fitting selects second-order fitting.
7. The method of detector measurement based prediction of neutron flux in a core of claim 1, wherein: in the step A, determining a past time point t according to the sampling time interval of the reactor core neutron flux on-line monitoring system0，t1，...，ti-2，ti-1And a future point in time ti+1，ti+2,.., and only the past time point t is retained0，t1，...，ti-2，ti-1In-core detector measurement values d (r) with determined change trend at different positions of reactor corem，t0)，d(rm，t1)，...，d(rm，ti)，...。
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