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

本发明公开了一种基于探测器测量值的堆芯中子通量预测方法，在不同时间点从堆内探测系统中读取并记录堆芯不同位置的堆内探测器测量值，拟合过去时间点和当前时间点的堆内探测器测量值，外推堆内探测器测量值，采用堆芯燃料管理程序模拟计算不同时间点的中子通量，进行本征正交分解，计算未来时间点的堆芯中子通量预测值；通过堆内探测器测量值的预测，结合堆芯中子通量在线重构方法，避免了更改原有堆芯中子通量在线监测系统的核心算法，而且对每一个位置的堆内探测器测量值单独进行仅包含时间一个自变量维度的拟合外推，既保证了预测精度，也减少了由于个别或局部探测器失效所引发的预测计算整体失效，实现了对堆芯中子通量的准确预测。

Figure 202010543625

The invention discloses a core neutron flux prediction method based on the measured values of detectors. The measured values of the in-core detectors at different positions of the core are read and recorded from the in-core detection system at different time points, and the past The measured values of the in-reactor detectors at the time point and the current time point are extrapolated, and the core fuel management program is used to simulate and calculate the neutron flux at different time points, perform eigenorthogonal decomposition, and calculate the future time The predicted value of the core neutron flux at the point; through the prediction of the measured value of the in-core detector, combined with the online reconstruction method of the core neutron flux, it avoids changing the core algorithm of the original core neutron flux online monitoring system , and the in-heap detector measurements at each location are individually extrapolated to fit only one independent variable dimension of time, which not only ensures the prediction accuracy, but also reduces the overall prediction calculation caused by individual or local detector failures. failure, an accurate prediction of the core neutron flux is achieved.

Figure 202010543625

Description

一种基于探测器测量值的堆芯中子通量预测方法A Prediction Method of Core Neutron Flux Based on Detector Measurements

技术领域technical field

本发明涉及发电厂核反应堆堆芯中子通量的预测手段领域，尤其涉及的是一种基于探测器测量值的堆芯中子通量预测方法。The invention relates to the field of prediction means for the core neutron flux of a nuclear reactor of a power plant, in particular to a core neutron flux prediction method based on the measured value of a detector.

背景技术Background technique

发电厂核反应堆堆芯功率分布在线监测系统，又称核反应堆堆芯中子通量在线监测系统，其功能和作用应该包括四个方面，即跟踪、监测、预测和报警，以实现对堆芯中子通量在线监测系统中已有设备的充分利用，对保障反应堆堆芯运行和安全，以及提高核电厂经济效益都具有重要意义。The on-line monitoring system for power distribution of nuclear reactor core in power plant, also known as on-line monitoring system for core neutron flux of nuclear reactor, its function and role should include four aspects, namely tracking, monitoring, prediction and alarm, so as to realize the monitoring of core neutron flux. The full utilization of the existing equipment in the flux online monitoring system is of great significance to ensure the operation and safety of the reactor core and to improve the economic benefits of the nuclear power plant.

为实现对核反应堆堆芯中子通量的在线监测，需要为该核反应堆额外安装的堆内中子探测器及信号处理器、中央处理器和各种数据和信号传输的导线，不论是这些元件本身的成本，还是由于这些元件的安装带来的反应堆的设计维护成本，例如原本密封的壁面因开孔所引入的屏蔽成本，包括在线监测计算算法在内，这些都会导致核电厂建设和运行成本的增加。In order to realize the online monitoring of the neutron flux in the core of a nuclear reactor, it is necessary to install additional in-core neutron detectors and signal processors, central processing units and wires for various data and signal transmission for the nuclear reactor, whether these components themselves The cost of the reactor, or the design and maintenance cost of the reactor due to the installation of these components, such as the shielding cost introduced by the opening of the originally sealed wall, including the online monitoring calculation algorithm, these will lead to the construction and operation cost of the nuclear power plant. Increase.

目前，中国国内和国外对核反应堆堆芯跟踪计算及中子通量在线监测计算的研究都已经较为充分，例如基于燃料管理程序的堆芯跟踪计算功能以及利用堆芯中子通量在线重构方法实现的在线监测。At present, domestic and foreign research on nuclear reactor core tracking calculation and neutron flux online monitoring calculation has been relatively sufficient, such as core tracking calculation function based on fuel management program and the use of core neutron flux online reconstruction method Realized online monitoring.

常见的核反应堆堆芯中子通量在线重构方法包括：谐波综合法、样条函数拟合法、耦合系数法、最小二乘法、多项式展开法、内部边界条件法、误差形状综合法、权重因子法、普通Kriging法和本征正交分解法。Common nuclear reactor core neutron flux online reconstruction methods include: harmonic synthesis method, spline function fitting method, coupling coefficient method, least square method, polynomial expansion method, internal boundary condition method, error shape synthesis method, weight factor method, ordinary Kriging method and eigenorthogonal decomposition method.

但是，在对核反应堆堆芯中子通量的预测方面的研究却很少，在对核反应堆堆芯所处状态的报警方面也鲜有报道；堆芯中子通量预测计算与堆芯中子通量在线监测计算最大的不同点在于，核反应堆堆芯中子通量预测计算是一种包括时间维度的计算，是对时间变量的刻画，若考虑将已有的堆芯中子通量在线重构方法用于预测计算中，除基于函数展开思想的谐波综合法和本征正交分解法可以将时间变量引入之外，其他的计算方法均无法引入时间变量，而早期开发的堆芯中子通量在线监测系统的核心算法已经确定，更改算法并不符合对系统已有设备充分利用的初衷。However, there are few studies on the prediction of the neutron flux in the core of a nuclear reactor, and there are few reports on the alarm of the state of the core of the nuclear reactor. The biggest difference between on-line monitoring and calculation of nuclear reactor core neutron flux is that the calculation of nuclear reactor core neutron flux is a calculation including the time dimension, which is a characterization of time variables. If considering the online reconstruction of the existing core neutron flux The method is used in the prediction calculation. Except for the harmonic synthesis method and the eigenorthogonal decomposition method based on the function expansion idea, which can introduce time variables, other calculation methods cannot introduce time variables. The core algorithm of the flux online monitoring system has been determined, and changing the algorithm does not meet the original intention of making full use of the existing equipment in the system.

因此，不论是从科学研究发展进程角度还是从工程应用的角度，都需要研究出一种合适且实用的核反应堆堆芯中子通量预测方法。Therefore, whether from the perspective of scientific research development process or from the perspective of engineering application, it is necessary to develop a suitable and practical nuclear reactor core neutron flux prediction method.

发明内容SUMMARY OF THE INVENTION

为解决上述技术问题，本发明提供一种基于探测器测量值的堆芯中子通量预测方法，可避免更改原有堆芯中子通量在线监测系统的核心算法，实现对堆芯中子通量的准确预测。In order to solve the above technical problems, the present invention provides a method for predicting the core neutron flux based on the measured value of the detector, which can avoid changing the core algorithm of the original core neutron flux on-line monitoring system, and realize the prediction of the core neutron flux. Accurate prediction of flux.

本发明的技术方案如下：一种基于探测器测量值的堆芯中子通量预测方法，包括以下步骤：The technical scheme of the present invention is as follows: a method for predicting the core neutron flux based on the measured value of the detector, comprising the following steps:

A、在根据堆芯每一个探测器所处位置的过去时间点

Figure DEST_PATH_IMAGE002
、当前时间点
Figure DEST_PATH_IMAGE004
和未来时间点
Figure DEST_PATH_IMAGE006
，从堆芯中子通量在线监测系统中读取并记录不同时间点堆芯不同位置的堆内探测器测量值
Figure DEST_PATH_IMAGE008
；其中，
Figure DEST_PATH_IMAGE010
表示堆内探测器位置，
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，M为堆内探测器数目；A. At the past time point according to the position of each detector in the core
Figure DEST_PATH_IMAGE002
, the current time
Figure DEST_PATH_IMAGE004
and future time
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, read and record the measured values of the in-core detectors at different positions of the core at different time points from the on-line monitoring system of core neutron flux
Figure DEST_PATH_IMAGE008
;in,
Figure DEST_PATH_IMAGE010
represents the position of the detector in the heap,
Figure DEST_PATH_IMAGE012
, M is the number of detectors in the heap;

B、以时间为变量，将过去时间点

Figure 587721DEST_PATH_IMAGE002
和当前时间点
Figure DEST_PATH_IMAGE013
堆芯不同位置的堆内探测器测量值
Figure DEST_PATH_IMAGE015
进行拟合，得到每一个堆内探测器测量值随时间变化函数
Figure DEST_PATH_IMAGE017
；B. Using time as a variable, the past time point
Figure 587721DEST_PATH_IMAGE002
and the current time
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In-core detector measurements at different positions in the core
Figure DEST_PATH_IMAGE015
Fitting to obtain the time-dependent function of each in-heap detector measurement
Figure DEST_PATH_IMAGE017
;

C、根据堆内探测器测量值随时间变化函数

Figure DEST_PATH_IMAGE019
，对堆内探测器测量值进行外推，得到未来时间点
Figure 64226DEST_PATH_IMAGE006
堆芯不同位置的堆内探测器测量值的预测值
Figure 797827DEST_PATH_IMAGE015
，
Figure 315134DEST_PATH_IMAGE012
；C. According to the time-varying function of the measured value of the in-heap detector
Figure DEST_PATH_IMAGE019
, extrapolate the in-heap detector measurements to obtain future time points
Figure 64226DEST_PATH_IMAGE006
Predicted values of in-core detector measurements at different positions in the core
Figure 797827DEST_PATH_IMAGE015
,
Figure 315134DEST_PATH_IMAGE012
;

D、采用堆芯燃料管理程序模拟计算不同时间点堆芯不同位置的中子通量

Figure DEST_PATH_IMAGE021
，
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，N为模拟计算的时间点数目；D. Use the core fuel management program to simulate and calculate the neutron flux at different positions of the core at different time points
Figure DEST_PATH_IMAGE021
,
Figure DEST_PATH_IMAGE023
, N is the number of time points for simulation calculation;

E、对不同时间点堆芯不同位置的中子通量

Figure DEST_PATH_IMAGE025
进行本征正交分解，获得本征正交基函数
Figure DEST_PATH_IMAGE027
；E. Neutron flux at different positions of the core at different time points
Figure DEST_PATH_IMAGE025
Perform eigenorthogonal decomposition to obtain eigenorthogonal basis functions
Figure DEST_PATH_IMAGE027
;

F、将本征正交基函数

Figure 9551DEST_PATH_IMAGE027
结合步骤C未来时间点
Figure DEST_PATH_IMAGE028
堆芯不同位置的堆内探测器测量值的预测值
Figure 945540DEST_PATH_IMAGE015
，分别计算未来时间点
Figure 595964DEST_PATH_IMAGE006
堆芯不同位置的堆芯中子通量预测值
Figure DEST_PATH_IMAGE030
。F. The eigenorthogonal basis function
Figure 9551DEST_PATH_IMAGE027
Combine step C with future time points
Figure DEST_PATH_IMAGE028
Predicted values of in-core detector measurements at different positions in the core
Figure 945540DEST_PATH_IMAGE015
, respectively, to calculate future time points
Figure 595964DEST_PATH_IMAGE006
Predicted values of core neutron flux at different positions of the core
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.

所述的基于探测器测量值的堆芯中子通量预测方法，其中：在步骤F中，根据堆内探测器测量值的预测值

Figure DEST_PATH_IMAGE032
计算堆芯中子通量预测值
Figure DEST_PATH_IMAGE034
，
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为系数。The method for predicting the core neutron flux based on the measured value of the detector, wherein: in step F, according to the predicted value of the measured value of the detector in the reactor
Figure DEST_PATH_IMAGE032
Calculate core neutron flux predictions
Figure DEST_PATH_IMAGE034
,
Figure DEST_PATH_IMAGE036
is the coefficient.

所述的基于探测器测量值的堆芯中子通量预测方法，其中：先根据最小二乘原理计算系数

Figure DEST_PATH_IMAGE037
，再根据本征正交基函数
Figure DEST_PATH_IMAGE038
计算堆芯中子通量预测值
Figure 644691DEST_PATH_IMAGE030
。The method for predicting the core neutron flux based on the measured value of the detector, wherein: the coefficient is first calculated according to the principle of least squares
Figure DEST_PATH_IMAGE037
, and then according to the eigenorthogonal basis function
Figure DEST_PATH_IMAGE038
Calculate core neutron flux predictions
Figure 644691DEST_PATH_IMAGE030
.

所述的基于探测器测量值的堆芯中子通量预测方法，其中：在步骤D~F中，若原有堆芯中子通量在线监测系统的核心算法为谐波综合法或样条函数拟合法，则采用谐波综合法或样条函数拟合法替换本征正交分解法。The method for predicting the core neutron flux based on the measured value of the detector, wherein: in steps D to F, if the core algorithm of the original core neutron flux online monitoring system is a harmonic synthesis method or a spline function If the fitting method is adopted, the eigenorthogonal decomposition method is replaced by the harmonic synthesis method or the spline function fitting method.

所述的基于探测器测量值的堆芯中子通量预测方法，其中：在步骤D中，模拟计算的时间点包含堆芯平均燃耗、硼浓度、控制棒位置、相对功率水平的堆芯状态。The method for predicting the core neutron flux based on the measured value of the detector, wherein: in step D, the time point of the simulation calculation includes the average core burnup, the boron concentration, the position of the control rod, and the relative power level of the core state.

所述的基于探测器测量值的堆芯中子通量预测方法，其中：在步骤C中，未来时间点

Figure 792119DEST_PATH_IMAGE006
的个数为2~4个。The method for predicting the core neutron flux based on the measured value of the detector, wherein: in step C, a future time point
Figure 792119DEST_PATH_IMAGE006
The number is 2~4.

所述的基于探测器测量值的堆芯中子通量预测方法，其中：在步骤B中，拟合的方法采用样条函数拟合或简单多项式拟合，且拟合的阶数选择二阶拟合。The method for predicting the core neutron flux based on the measured value of the detector, wherein: in step B, the fitting method adopts spline function fitting or simple polynomial fitting, and the fitting order selects the second order fit.

所述的基于探测器测量值的堆芯中子通量预测方法，其中：在步骤A中，根据堆芯中子通量在线监测系统采样时间间隔确定过去时间点

Figure DEST_PATH_IMAGE039
和未来时间点
Figure 499175DEST_PATH_IMAGE006
的个数，且仅保留过去时间点
Figure DEST_PATH_IMAGE040
堆芯不同位置有确定变化趋势的堆内探测器测量值
Figure 472947DEST_PATH_IMAGE008
。The method for predicting the core neutron flux based on the measured value of the detector, wherein: in step A, the past time point is determined according to the sampling time interval of the core neutron flux online monitoring system
Figure DEST_PATH_IMAGE039
and future time
Figure 499175DEST_PATH_IMAGE006
number of , and only keep past time points
Figure DEST_PATH_IMAGE040
In-core detector measurements with definite trends at different positions of the core
Figure 472947DEST_PATH_IMAGE008
.

本发明所提供的一种基于探测器测量值的堆芯中子通量预测方法，通过堆内探测器测量值的预测，结合堆芯中子通量在线重构方法，避免了更改原有堆芯中子通量在线监测系统的核心算法，而且对每一个位置的堆内探测器测量值单独进行仅包含时间一个自变量维度的拟合外推，既保证了预测精度，也减少了由于个别或局部探测器失效所引发的预测计算整体失效，实现了对堆芯中子通量的准确预测。The invention provides a method for predicting the core neutron flux based on the measured value of the detector. Through the prediction of the measured value of the detector in the reactor and the online reconstruction method of the core neutron flux, the modification of the original reactor is avoided. The core algorithm of the core neutron flux online monitoring system, and the fitting and extrapolation of the in-core detector measurement value at each position only includes time as an independent variable dimension, which not only ensures the prediction accuracy, but also reduces the number of Or the overall failure of the prediction calculation caused by the failure of the local detector, and the accurate prediction of the neutron flux in the core is realized.

附图说明Description of drawings

在此描述的附图仅用于解释目的，而非意图以任何方式来限制本发明公开的范围；图中各部件的形状和比例尺寸等仅为示意性的，用于帮助对本发明的理解，并非是具体限定本发明各部件的形状和比例尺寸；本领域的技术人员在本发明的教导下，可以根据具体情况选择各种可能的形状和比例尺寸来实施本发明。The drawings described herein are for illustrative purposes only, and are not intended to limit the scope of the present disclosure in any way; the shapes and proportions of the various components in the drawings are only schematic and are used to help the understanding of the present invention, The shape and scale of each component of the present invention are not specifically limited; those skilled in the art can choose various possible shapes and scales according to specific conditions to implement the present invention under the teaching of the present invention.

图1是本发明基于探测器测量值的堆芯中子通量预测方法的总体流程图；Fig. 1 is the overall flow chart of the core neutron flux prediction method based on the detector measurement value of the present invention;

图2是本发明基于探测器测量值的堆芯中子通量预测方法所用典型压水堆堆芯燃料实施例的布置示意图；2 is a schematic diagram of the layout of a typical PWR core fuel embodiment used in the core neutron flux prediction method based on the detector measurement value of the present invention;

图3是本发明图2中的E09通道堆内探测器测量值随时间变化示意图；Fig. 3 is the schematic diagram of the time variation of the measured value of the E09 channel in-stack detector in Fig. 2 of the present invention;

图4是本发明图2中的N06通道堆内探测器测量值随时间变化示意图。FIG. 4 is a schematic diagram showing the variation of the measured value of the N06 channel in-stack detector with time in FIG. 2 of the present invention.

具体实施方式Detailed ways

以下将结合附图，对本发明的具体实施方式和实施例加以详细说明，所描述的具体实施例仅用以解释本发明，并非用于限定本发明的具体实施方式。The specific embodiments and embodiments of the present invention will be described in detail below with reference to the accompanying drawings. The specific embodiments described are only used to explain the present invention, and are not used to limit the specific embodiments of the present invention.

如图1所示，图1是本发明基于探测器测量值的堆芯中子通量预测方法的总体流程图，本发明基于探测器测量值的堆芯中子通量预测方法包括以下步骤：As shown in FIG. 1 , FIG. 1 is an overall flow chart of the method for predicting the core neutron flux based on the measured value of the detector according to the present invention. The method for predicting the core neutron flux based on the measured value of the detector according to the present invention includes the following steps:

步骤S210、在不同时间点从堆芯中子通量在线监测系统中读取并记录堆芯不同位置的堆内探测器测量值；即记录堆芯每一个探测器所处位置的过去时间点

Figure 4160DEST_PATH_IMAGE002
、当前时间点
Figure 860121DEST_PATH_IMAGE013
和未来时间点
Figure 964343DEST_PATH_IMAGE006
，从堆内探测系统(即堆芯中子通量在线监测系统)中读取并记录不同时间点堆芯不同位置的堆内探测器测量值
Figure DEST_PATH_IMAGE041
；其中，
Figure 995884DEST_PATH_IMAGE010
表示堆内探测器位置，
Figure 261780DEST_PATH_IMAGE012
，M为堆内探测器数目；Step S210: Read and record the measured values of the in-core detectors at different positions of the reactor core from the on-line monitoring system for neutron flux in the reactor core at different time points; that is, record the past time points of the position of each detector in the reactor core
Figure 4160DEST_PATH_IMAGE002
, the current time
Figure 860121DEST_PATH_IMAGE013
and future time
Figure 964343DEST_PATH_IMAGE006
, read and record the measured values of the in-core detectors at different positions of the core at different time points from the in-core detection system (ie, the core neutron flux online monitoring system)
Figure DEST_PATH_IMAGE041
;in,
Figure 995884DEST_PATH_IMAGE010
represents the position of the detector in the heap,
Figure 261780DEST_PATH_IMAGE012
, M is the number of detectors in the heap;

步骤S220、以时间为变量，将步骤S210中记录的过去时间点

Figure 605037DEST_PATH_IMAGE040
堆芯不同位置的堆内探测器测量值
Figure 889781DEST_PATH_IMAGE041
，与当前时间点
Figure 634883DEST_PATH_IMAGE004
堆芯不同位置的堆内探测器测量值
Figure 274943DEST_PATH_IMAGE008
进行拟合，得到每一个堆内探测器测量值随时间变化函数
Figure DEST_PATH_IMAGE042
；Step S220, with time as a variable, the past time point recorded in step S210 is
Figure 605037DEST_PATH_IMAGE040
In-core detector measurements at different positions in the core
Figure 889781DEST_PATH_IMAGE041
, with the current time point
Figure 634883DEST_PATH_IMAGE004
In-core detector measurements at different positions in the core
Figure 274943DEST_PATH_IMAGE008
Fitting to obtain the time-dependent function of each in-heap detector measurement
Figure DEST_PATH_IMAGE042
;

步骤S230、根据步骤S220获得的堆内探测器测量值随时间变化函数

Figure 807293DEST_PATH_IMAGE019
，对堆内探测器测量值进行外推，得到未来时间点
Figure 253318DEST_PATH_IMAGE006
堆芯不同位置的堆内探测器测量值的预测值
Figure 790610DEST_PATH_IMAGE041
，
Figure 398309DEST_PATH_IMAGE012
；Step S230, according to the time-varying function of the measured value of the in-heap detector obtained in step S220
Figure 807293DEST_PATH_IMAGE019
, extrapolate the in-heap detector measurements to obtain future time points
Figure 253318DEST_PATH_IMAGE006
Predicted values of in-core detector measurements at different positions in the core
Figure 790610DEST_PATH_IMAGE041
,
Figure 398309DEST_PATH_IMAGE012
;

步骤S240、采用堆芯燃料管理程序模拟计算不同时间点堆芯不同位置的中子通量

Figure 716157DEST_PATH_IMAGE021
，
Figure 637977DEST_PATH_IMAGE023
，N为模拟计算的时间点数目；Step S240, using the core fuel management program to simulate and calculate the neutron flux at different positions of the core at different time points
Figure 716157DEST_PATH_IMAGE021
,
Figure 637977DEST_PATH_IMAGE023
, N is the number of time points for simulation calculation;

步骤S250、对步骤S240中模拟计算出的不同时间点堆芯不同位置的中子通量

Figure 859136DEST_PATH_IMAGE025
进行本征正交分解，获得本征正交基函数
Figure DEST_PATH_IMAGE043
；Step S250, the neutron fluxes at different positions of the core at different time points calculated by the simulation in step S240
Figure 859136DEST_PATH_IMAGE025
Perform eigenorthogonal decomposition to obtain eigenorthogonal basis functions
Figure DEST_PATH_IMAGE043
;

步骤S260、将步骤S250获得的本征正交基函数

Figure 44261DEST_PATH_IMAGE038
，结合步骤S230外推获得的未来时间点
Figure 787089DEST_PATH_IMAGE006
堆芯不同位置的堆内探测器测量值的预测值
Figure 574917DEST_PATH_IMAGE015
，分别计算未来时间点
Figure 382073DEST_PATH_IMAGE006
堆芯不同位置的堆芯中子通量预测值
Figure 534837DEST_PATH_IMAGE030
。Step S260, use the eigenorthogonal basis function obtained in step S250
Figure 44261DEST_PATH_IMAGE038
, combined with the future time point obtained by extrapolation in step S230
Figure 787089DEST_PATH_IMAGE006
Predicted values of in-core detector measurements at different positions in the core
Figure 574917DEST_PATH_IMAGE015
, respectively, to calculate future time points
Figure 382073DEST_PATH_IMAGE006
Predicted values of core neutron flux at different positions of the core
Figure 534837DEST_PATH_IMAGE030
.

本发明基于探测器测量值的堆芯中子通量预测方法中的步骤S210~S230是实时计算，步骤S240~S260是提前计算并存储；在进行中子通量预测计算之前，首先进行的是堆内探测器测量值的预测计算，然后在此基础上再结合本征正交分解法，实现了对堆芯中子通量的准确预测。Steps S210-S230 in the core neutron flux prediction method based on the detector measurement value of the present invention are real-time calculation, and steps S240-S260 are calculated and stored in advance; The prediction calculation of the measured value of the in-core detector, and then combined with the eigenorthogonal decomposition method on this basis, realizes the accurate prediction of the core neutron flux.

与现有技术相比，本发明基于探测器测量值的堆芯中子通量预测方法具有以下的突出优点：Compared with the prior art, the core neutron flux prediction method based on the detector measurement value of the present invention has the following outstanding advantages:

1）对堆芯中子通量的预测，体现在对堆内探测器测量值的预测，对堆芯中子通量在线监测系统核心算法没有影响，更便于升级和移植，也符合对系统已有设备充分利用的初衷；1) The prediction of the core neutron flux is reflected in the prediction of the measured values of the detectors in the reactor. Have the original intention of making full use of the equipment;

2）对每一个位置的堆内探测器测量值都是单独进行拟合外推和预测，避免了由于个别或局部探测器失效引起的预测计算整体失效；2) The measured values of the in-stack detectors at each position are individually fitted, extrapolated and predicted, which avoids the overall failure of the prediction calculation caused by the failure of individual or local detectors;

3）对堆内探测器测量值的拟合与外推，仅包含时间一个自变量维度，确保了堆芯中子通量预测计算的计算精度。3) The fitting and extrapolation of the measured values of the in-core detectors only include time as an independent variable dimension, which ensures the calculation accuracy of the core neutron flux prediction calculation.

在步骤S210中，不指定过去时间点

Figure 561699DEST_PATH_IMAGE002
的个数以及未来时间点
Figure 887638DEST_PATH_IMAGE006
的个数，具体数量可根据实际应用情况而定；较好的是，根据堆芯中子通量在线监测系统采样时间间隔的实际情况确定过去时间点
Figure 254028DEST_PATH_IMAGE002
和未来时间点
Figure 374431DEST_PATH_IMAGE006
的个数，而仅保留过去时间点
Figure 655633DEST_PATH_IMAGE040
堆芯不同位置有确定变化趋势的堆内探测器测量值
Figure 722946DEST_PATH_IMAGE008
即可。In step S210, the past time point is not specified
Figure 561699DEST_PATH_IMAGE002
number of and future time points
Figure 887638DEST_PATH_IMAGE006
The specific number can be determined according to the actual application; it is better to determine the past time point according to the actual situation of the sampling time interval of the core neutron flux online monitoring system
Figure 254028DEST_PATH_IMAGE002
and future time
Figure 374431DEST_PATH_IMAGE006
number of , and only keep past time points
Figure 655633DEST_PATH_IMAGE040
In-core detector measurements with definite trends at different positions of the core
Figure 722946DEST_PATH_IMAGE008
That's it.

在步骤S220中，不限制堆内探测器测量值的拟合方法，所采用的拟合方法不限，但因为仅有一个时间的自变量，考虑到自变量数目以及因变量的变化范围和趋势，推荐采用样条函数拟合或简单多项式拟合，拟合的阶数根据实际应用情况而定，推荐选择二阶拟合即可满足精度要求。In step S220, the fitting method of the measured values of the in-stack detector is not limited, and the fitting method used is not limited, but since there is only one independent variable of time, the number of independent variables and the variation range and trend of the dependent variable are considered. , it is recommended to use spline function fitting or simple polynomial fitting. The order of fitting depends on the actual application. It is recommended to choose second-order fitting to meet the accuracy requirements.

在步骤S230中，也不指定未来时间点

Figure 740581DEST_PATH_IMAGE006
的个数，对未来时间点的外推，过长时间的外推会引入偏差累或造成偏差累积，但由于在每一个堆内探测器测量值的采集时间点均可做未来时间点
Figure 297464DEST_PATH_IMAGE006
的预测，因此，推荐未来时间点
Figure 298918DEST_PATH_IMAGE006
的个数优选2~4个。In step S230, a future time point is also not specified
Figure 740581DEST_PATH_IMAGE006
For the extrapolation of future time points, extrapolation for a long time will introduce deviation accumulation or cause deviation accumulation, but because the acquisition time point of each in-stack detector measurement value can be used as a future time point
Figure 297464DEST_PATH_IMAGE006
forecasts, and therefore recommend future points in time
Figure 298918DEST_PATH_IMAGE006
The number is preferably 2 to 4.

在步骤S240中，也不限制具体的堆芯燃料管理程序，但模拟计算的时间点，推荐参照堆芯中子通量在线重构中的样本选取方法，应包含尽量多的堆芯平均燃耗、硼浓度、控制棒位置、相对功率水平等堆芯状态，以提高预测准确度。In step S240, the specific core fuel management program is not limited, but it is recommended to refer to the sample selection method in the online reconstruction of core neutron flux at the time point of the simulation calculation, which should include as many average core burnups as possible. , boron concentration, control rod position, relative power level and other core states to improve prediction accuracy.

在步骤S260中，由于堆内探测器测量值的预测值有

Figure DEST_PATH_IMAGE045
表达式，因此根据堆内探测器测量值的预测值
Figure DEST_PATH_IMAGE046
，先计算系数
Figure 543824DEST_PATH_IMAGE036
，再计算堆芯中子通量预测值
Figure 415965DEST_PATH_IMAGE034
；优选地，先根据最小二乘原理计算系数
Figure 409329DEST_PATH_IMAGE036
，再根据本征正交基函数
Figure DEST_PATH_IMAGE047
计算堆芯中子通量预测值
Figure 794349DEST_PATH_IMAGE030
。In step S260, since the predicted value of the measured value of the in-heap detector has
Figure DEST_PATH_IMAGE045
expression, so the predicted value based on the in-heap probe measurements
Figure DEST_PATH_IMAGE046
, first calculate the coefficient
Figure 543824DEST_PATH_IMAGE036
, and then calculate the predicted core neutron flux
Figure 415965DEST_PATH_IMAGE034
; preferably, the coefficients are first calculated according to the principle of least squares
Figure 409329DEST_PATH_IMAGE036
, and then according to the eigenorthogonal basis function
Figure DEST_PATH_IMAGE047
Calculate core neutron flux predictions
Figure 794349DEST_PATH_IMAGE030
.

在步骤S250~S260中，若原有堆芯中子通量在线监测系统的核心算法为谐波综合法或样条函数拟合法等其他算法，则采用谐波综合法或样条函数拟合法替换本征正交分解法。In steps S250-S260, if the core algorithm of the original core neutron flux online monitoring system is other algorithms such as the harmonic synthesis method or the spline function fitting method, the harmonic synthesis method or the spline function fitting method is used to replace the original core algorithm. Qualitative Orthogonal Decomposition.

在本发明基于探测器测量值的堆芯中子通量预测方法的优选实施方式中，为验证本发明基于探测器测量值的堆芯中子通量预测方法的有效性，本发明采用了典型压水堆堆芯设计验证算例，由于对堆芯中子通量的预测精度取决于对堆内探测器测量值的预测精度，因此本发明仅考察堆内探测器测量值随时间的变化趋势是否易于捕捉和预测即可。In a preferred embodiment of the method for predicting the core neutron flux based on the measured value of the detector of the present invention, in order to verify the validity of the method for predicting the core neutron flux based on the measured value of the detector of the present invention, the present invention adopts a typical For the verification example of the PWR core design, since the prediction accuracy of the core neutron flux depends on the prediction accuracy of the measured values of the in-reactor detectors, the present invention only examines the variation trend of the measured values of the in-reactor detectors with time. Whether it is easy to capture and predict.

结合图2所示，图2是本发明基于探测器测量值的堆芯中子通量预测方法所用典型压水堆堆芯燃料实施例的布置示意图，不同方格中的数字代表燃料组内不同类型的可燃毒物棒数目，1.6 w/o U-235、2.4 w/o U-235和3.1 w/o U-235分别代表可燃毒物棒的燃料富集度为1.6%、2.4%、3.1%；。With reference to Figure 2, Figure 2 is a schematic diagram of the layout of a typical PWR core fuel example used in the core neutron flux prediction method based on the detector measurement value of the present invention. The numbers in different squares represent different fuel groups. The number of types of burnable poison rods, 1.6 w/o U-235, 2.4 w/o U-235 and 3.1 w/o U-235 represent the fuel enrichment of burnable poison rods of 1.6%, 2.4% and 3.1%, respectively; .

结合图3和图4所示，图3是本发明图2中的E09通道堆内探测器测量值随时间变化示意图，图4是本发明图2中的N06通道堆内探测器测量值随时间变化示意图；其中，横坐标x均为采集时间点，单位为秒，纵坐标y均为堆内探测器测量值；由图3和图4可知，在以秒为量级的采集时间间隔内，E09通道或N06通道的堆内探测器测量值随时间变化曲线特性已经变得易于描述，采用一次或二次多项式的拟合形式即可，且拟合的精度较高。3 and 4, FIG. 3 is a schematic diagram of the measured value of the E09 channel in-stack detector in FIG. 2 of the present invention over time, and FIG. 4 is the N06 channel in-stack detector in FIG. 2 of the present invention. The measured value of the detector changes over time Schematic diagram of changes; in which, the abscissa x is the acquisition time point, the unit is seconds, and the ordinate y is the measured value of the in-heap detector; it can be seen from Figure 3 and Figure 4 that in the acquisition time interval of the order of seconds, The time-dependent curve characteristics of the measured values of the in-stack detectors of the E09 channel or N06 channel have become easy to describe, and the fitting form of first-order or second-order polynomial can be used, and the fitting accuracy is high.

由此可见，本发明提供的基于探测器测量值的堆芯中子通量预测方法，应用在堆芯中子通量预测计算中，通过对堆内探测器测量值的预测，较好地避免了对堆芯中子通量在线监测系统核心算法的更改，且对每一个位置的堆内探测器测量值单独进行仅包含时间一个自变量维度的拟合外推，在保证了预测精度的同时也减少了由于个别或局部探测器失效引起的预测计算整体失效，实现了对堆芯中子通量的准确预测。It can be seen that the method for predicting the core neutron flux based on the measured value of the detector provided by the present invention is applied in the prediction calculation of the core neutron flux. The core algorithm of the core neutron flux online monitoring system has been changed, and the in-core detector measurements at each position are individually fitted and extrapolated with only one independent variable dimension of time, which ensures the prediction accuracy while at the same time. The overall failure of prediction calculations due to individual or local detector failures is also reduced, enabling accurate prediction of core neutron fluxes.

应当理解的是，以上所述仅为本发明的较佳实施例而已，并不足以限制本发明的技术方案，对本领域普通技术人员来说，在本发明的精神和原则之内，可以根据上述说明加以增减、替换、变换或改进，例如，本发明步骤240~260是根据堆芯中子通量在线重构方法本征正交分解法进行描述的，若原有的堆芯中子通量在线监测系统的核心算法为谐波综合法或样条函数拟合法等其他算法，则相应对照修改步骤240~260即可，以实现方便的移植；而所有这些增减、替换、变换或改进后的技术方案，都应属于本发明所附权利要求的保护范围。It should be understood that the above are only preferred embodiments of the present invention, and are not sufficient to limit the technical solutions of the present invention. For those of ordinary skill in the art, within the spirit and principles of the present invention, they can For example, steps 240 to 260 of the present invention are described according to the eigenorthogonal decomposition method of the on-line reconstruction method of the core neutron flux. If the original core neutron flux The core algorithm of the online monitoring system is other algorithms such as harmonic synthesis method or spline function fitting method, and steps 240 to 260 can be modified accordingly, so as to realize convenient transplantation; All technical solutions should belong to the protection scope of the appended claims of the present invention.

Claims (7)

1.一种基于探测器测量值的堆芯中子通量预测方法，其特征在于，包括以下步骤：1. A method for predicting core neutron flux based on detector measurement value, characterized in that, comprising the following steps: A、在根据堆芯每一个探测器所处位置的过去时间点t0，t1，...，ti-2，ti-1、当前时间点ti和未来时间点ti+1，ti+2，...，从堆芯中子通量在线监测系统中读取并记录不同时间点堆芯不同位置的堆内探测器测量值d(rm，to)，d(rm，t1)，...，d(rm，ti)，...；其中，rm表示堆内探测器位置，m＝1，2，...，M，M为堆内探测器数目；A. At past time points t 0 , t 1 , ..., t i-2 , t i-1 , current time point t i and future time point t i+1 according to the position of each detector in the core , t i+2 ,..., read and record the measured values d(r m , t o ), d( rm , t 1 ), ..., d(rm , t i ) , ...; wherein, rm represents the position of the detector in the heap, m =1, 2, ..., M, M is the heap the number of internal detectors; B、以时间为变量，将过去时间点t0，t1，...，ti-2，ti-1和当前时间点ti堆芯不同位置的堆内探测器测量值d(rm，t0)，d(rm，t1)，...，d(rm，ti)，...进行拟合，得到每一个堆内探测器测量值随时间变化函数D(rm，t)，m＝1，2，...，M； B. Taking time as a variable, use the past time points t 0 , t 1 , . m , t 0 ), d(r m , t 1 ), ..., d(rm , t i ), ... are fitted to obtain the time-varying function D( r m , t), m=1, 2, ..., M; C、根据堆内探测器测量值随时间变化函数D(rm，t)，对堆内探测器测量值进行外推，得到未来时间点ti+1，ti+2，...堆芯不同位置的堆内探测器测量值的预测值d(rm，ti+1)，d(rm，ti-2)，...，m＝1，2，...，M；C. According to the time-varying function D(r m , t) of the measured values of the in-heap detectors, extrapolate the measured values of the in-heap detectors to obtain future time points t i+1 , t i+2 , ... heaps Predicted values of in-stack detector measurements at different positions of the core d(r m , t i+1 ), d(r m , t i-2 ), ..., m=1, 2, ..., M ; D、采用堆芯燃料管理程序模拟计算不同时间点堆芯不同位置的中子通量
Figure FDA0003587273900000011
c＝1，2，...，N，N为模拟计算的时间点数目；D. Use the core fuel management program to simulate and calculate the neutron flux at different positions of the core at different time points
Figure FDA0003587273900000011
c=1, 2, ..., N, N is the number of time points for simulation calculation; E、对不同时间点堆芯不同位置的中子通量
Figure FDA0003587273900000012
进行本征正交分解，获得本征正交基函数ψn(r)，n＝1，2，...，N；E. Neutron flux at different positions of the core at different time points
Figure FDA0003587273900000012
Perform eigenorthogonal decomposition to obtain eigenorthogonal basis functions ψ n (r), n=1, 2,...,N; F、将本征正交基函数ψn(r)结合步骤C未来时间点ti+1，ti+2，...堆芯不同位置的堆内探测器测量值的预测值d(rm，ti-1)，d(rm，ti-2)，...有表达式
Figure FDA0003587273900000013
其中，x＝1，2，...；先计算系数an，再根据本征正交基函数ψn(r)及
Figure FDA0003587273900000014
分别计算未来时间点ti+1，ti+2，...堆芯不同位置的堆芯中子通量预测值
Figure FDA0003587273900000015
F. Combine the intrinsic orthonormal basis function ψ n (r ) with the predicted value d(r m , t i-1 ), d(r m , t i-2 ), ... have expressions
Figure FDA0003587273900000013
Among them, x=1, 2,...; first calculate the coefficient an, and then according to the eigenorthogonal basis function ψ n ( r) and
Figure FDA0003587273900000014
Calculate the predicted values of core neutron flux at different positions of the core at future time points t i+1 , t i+2 , ... respectively
Figure FDA0003587273900000015
 2.根据权利要求1所述的基于探测器测量值的堆芯中子通量预测方法，其特征在于：根据最小二乘原理计算系数an。2 . The method for predicting core neutron flux based on detector measurement values according to claim 1 , wherein the coefficient an is calculated according to the principle of least squares. 3 . 3.根据权利要求1所述的基于探测器测量值的堆芯中子通量预测方法，其特征在于：在步骤D～F中，若原有堆芯中子通量在线监测系统的核心算法为谐波综合法或样条函数拟合法，则采用谐波综合法或样条函数拟合法替换本征正交分解法。3 . The method for predicting core neutron flux based on the measured value of the detector according to claim 1 , wherein in steps D to F, if the core algorithm of the original core neutron flux online monitoring system is: 3 . If the harmonic synthesis method or the spline function fitting method is used, the eigenorthogonal decomposition method is replaced by the harmonic synthesis method or the spline function fitting method. 4.根据权利要求1所述的基于探测器测量值的堆芯中子通量预测方法，其特征在于：在步骤D中，模拟计算的时间点包含堆芯平均燃耗、硼浓度、控制棒位置、相对功率水平的堆芯状态。4 . The method for predicting core neutron flux based on detector measurement values according to claim 1 , wherein in step D, the time point of the simulation calculation includes average core burnup, boron concentration, control rods position, core state relative to power level. 5.根据权利要求1所述的基于探测器测量值的堆芯中子通量预测方法，其特征在于：在步骤C中，未来时间点ti+1，ti+2，...的个数为2～4个。5 . The method for predicting core neutron flux based on detector measurement values according to claim 1 , wherein in step C, the future time points t i+1 , t i+2 , . . . The number is 2 to 4. 6.根据权利要求1所述的基于探测器测量值的堆芯中子通量预测方法，其特征在于：在步骤B中，拟合的方法采用样条函数拟合或简单多项式拟合，且拟合的阶数选择二阶拟合。6. The method for predicting core neutron flux based on detector measurement values according to claim 1, wherein in step B, the fitting method adopts spline function fitting or simple polynomial fitting, and The order of fitting selects the second-order fitting. 7.根据权利要求1所述的基于探测器测量值的堆芯中子通量预测方法，其特征在于：在步骤A中，根据堆芯中子通量在线监测系统采样时间间隔确定过去时间点t0，t1，...，ti-2，ti-1和未来时间点ti+1，ti+2，...的个数，且仅保留过去时间点t0，t1，...，ti-2，ti-1堆芯不同位置有确定变化趋势的堆内探测器测量值d(rm，t0)，d(rm，t1)，...，d(rm，ti)，...。7 . The method for predicting core neutron flux based on detector measurement value according to claim 1 , wherein in step A, the past time point is determined according to the sampling time interval of the core neutron flux online monitoring system. 8 . The number of t 0 , t 1 , ..., t i-2 , t i-1 and future time points t i+1 , t i+2 , ..., and only the past time points t 0 , t are retained 1 , ..., t i-2 , t i-1 In-core detector measurements d(r m , t 0 ), d(r m , t 1 ), .. ., d(r m , t i ), . . .
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