CN113161028B - Reactivity measurement method based on correction signal optimization processing - Google Patents
Reactivity measurement method based on correction signal optimization processing Download PDFInfo
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Abstract
The invention discloses a reactivity measurement method based on correction signal optimization processing, which comprises the following steps: s1, maximum frequency sampling processing; s2, performing down-sampling processing by using a removing method; s3, evaluating the uncertainty of actual measurement; s4, correcting to obtain uncertainty of the corrected neutron signal sequence; s5, optimal judgment; s6, reactivity analysis: and performing reactivity measurement calculation analysis by adopting the optimal neutron signal sequence to obtain a reactivity measurement result, and synthesizing the uncertainty of the optimal neutron signal sequence to obtain the uncertainty corresponding to the reactivity measurement result.
Description
Technical Field
The invention relates to the field of nuclear reactor reactivity measurement and processing, in particular to a reactivity measurement method based on correction signal optimization processing.
Background
The reactivity measurement of the reactor core of the nuclear reactor mainly aims at the measurement processes of control rod integral value, rod clamping subcritical degree, shutdown depth and the like in the physical test process.
The commonly used reactivity measurement methods for nuclear power plants are: boron adjustment method, rod replacement method and dynamic rod carving method. The boron regulation method measures the micro and integral values of the control rod by regulating the boron concentration, but has long measuring time and high cost;
the rod changing method does not need to adjust boron, consumes a little short time and can measure the integral value of the control rod;
the dynamic rod-carving method can accurately measure the control rod integral value in a short time by inserting the control rod downwards and combining calculation analysis and actual measurement data, and is a method widely used by the conventional nuclear power station.
However, the above methods are generally used for reactivity measurements within about 2000pcm, with limitations for large reactivity measurements.
The most common measurement method for large reactivity is the rod drop method.
The basic principle of the rod dropping method is as follows: and (3) instantaneously dropping the control rod into the reactor in a critical state, measuring the change of the neutron counting rate along with time, and calculating the reactivity to be measured by combining the neutron counting rates before and after dropping the rod. According to the method, the rod drop is adopted, the quick measurement of the large reactivity such as the control rod integral value, the rod clamping subcritical degree and the shutdown depth can be realized, but the method is based on a point reactor model, the measurement result is easily influenced by the neutron flux space effect, and an error exists in the large reactivity measurement process. In order to obtain a more accurate measurement result with large reactivity, the measurement process of the rod drop method needs to be corrected based on three-dimensional space-time dynamics analysis.
In the process of reactivity measurement, a neutron signal is a key parameter for reactivity measurement, the quantity is influenced by factors such as statistical fluctuation, high-voltage ripples and electromagnetic interference in the measurement process, and the measurement result has certain uncertainty. Therefore, uncertainty analysis is needed in the reaction measurement process, measurement data are optimized, and the influence of uncertainty is reduced, so that the measurement efficiency and accuracy are improved.
At present, no other unit develops reactivity measurement method research based on correction signal optimization processing or reports of related patent technologies in China. Therefore, it is necessary to master an autonomized reactivity measurement method based on correction signal optimization processing according to the difference between the autonomous reactor core and the foreign reactor core, and to provide capability for efficient and accurate measurement of reactor core reactivity.
Disclosure of Invention
The invention aims to provide a reactivity measurement method based on correction signal optimization processing, which can reduce the influence of factors such as neutron signal statistical fluctuation, high-voltage ripples, electromagnetic interference and the like in the reactivity measurement process, make up the defects of the existing measurement method aiming at dynamic reactivity measurement, and improve the efficiency and the accuracy of reactor reactivity measurement.
The invention is realized by the following technical scheme:
a reactivity measurement method based on correction signal optimization processing comprises the following steps:
s1, maximum frequency sampling processing: when the reactor is brought into reactivity, neutron signal monitoring is carried out, and data acquisition set to the maximum sampling frequency is adoptedThe card samples the neutron signal; a group of neutron signal sequences I with the maximum sampling frequency fmax output by the data acquisition card fmax (ii) a The neutron signal sequence I fmax Includes I neutron signal data measured values, I 1 、I 2 、…I i (ii) a i represents a sampling point, and the size of i is determined according to fmax;
s2, removing the down-sampling processing by a method: partial data point pair neutron signal sequence I is eliminated by adopting equal intervals fmax Performing down-sampling processing for n times to obtain a neutron signal sequence I with the sampling frequency of f1 f1 … neutron signal sequence I with sampling frequency fn fn (ii) a f1 and fn are both smaller than fmax;
s3, evaluating the uncertainty of actual measurement: for neutron signal sequence I with sampling frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn Carrying out actual measurement uncertainty evaluation to obtain the actual measurement uncertainty of the neutron signal sequence under different sampling frequencies;
s4, correcting: neutron signal sequence I with correction factor to sampling frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn Correcting to obtain a corrected neutron signal sequence; correction factor-introduced uncertainty versus neutron signal sequence I with sampling frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn Carrying out uncertainty synthesis on the actual measurement uncertainty to obtain corrected synthesis uncertainty of the corrected neutron signal sequence;
s5, optimal judgment: according to the neutron signal sequence I with the corrected sampling frequency of f1 f1 Corrected synthetic uncertainty … neutron signal sequence I with sampling frequency fn fn The corrected synthesis uncertainty is subjected to optimal judgment, a corrected signal data set with the optimal uncertainty is selected from the corrected synthesis uncertainty, and a neutron signal sequence corresponding to the optimal uncertainty is recorded as an optimal neutron signal sequence;
s6, reactivity analysis: and performing reactivity measurement calculation analysis by adopting the optimal neutron signal sequence to obtain a reactivity measurement result, and synthesizing the uncertainty of the optimal neutron signal sequence to obtain the uncertainty corresponding to the reactivity measurement result.
The design principle of the invention is as follows:
in existing measurements, the environmental impact is generally not taken into account, but the measured neutron signal is directly substituted into the reactivity calculation.
The application field of the invention is reactivity measurement of nuclear reactors, the measurement environment is more complex, and the general influence factors are as follows: the signal statistics is influenced by factors such as fluctuation, high-voltage ripple, electromagnetic interference and the like; if the environmental influence is not considered and only the systematic error of the point-pile measurement model is considered, the obtained reactivity has certain uncertainty.
The invention needs to design a processing method, which effectively reduces the influence of the measuring environment; the invention carries out down-sampling processing on the corrected neutron signal and simultaneously constructs standard uncertainty to evaluate the uncertainty of the down-sampled neutron signal, thereby optimizing and reconstructing the actually measured and corrected data to reduce the uncertainty thereof and further reducing the influence of the actually measured environment. It can prefer a neutron signal group with the best uncertainty from these data groups, thus reducing the environmental impact; the optimal set of neutron signals selected by the neutron detector can be used for subsequent reactivity processing. In the invention, the neutron signal is subjected to down-sampling processing and neutron signal correction, the systematic error of a point stack measurement model is eliminated, the influence of uncertainty brought by a measurement environment is reduced, and finally reactivity calculation is carried out.
The invention firstly adopts the maximum frequency to sample, thus enough data points can be obtained by one-time sampling, and then adopts the average method to carry out down-sampling processing to form different data groups, thus directly obtaining the data groups with different frequencies under the same sampling environment, and the external environments of the data groups are the same. The traditional method is repeated sampling times, the measurement time is greatly increased in each sampling with different frequencies, the measurement effect is too low, and the environmental conditions of each measurement cannot be guaranteed to be completely the same, so that the comparison is not facilitated.
The actual measurement uncertainty evaluation refers to the uncertainty evaluation of the neutron signal obtained by the reactor in the actual environment, so that the uncertainty of the actual measurement neutron signal is obtained. The actual measurement uncertainty evaluation process is carried out relative to the removal method for reducing the sampling of the obtained actual measurement neutron signal, and specifically, the uncertainty of the neutron signal in a typical state can be adopted for calibrating the neutron signal, wherein the establishment of the uncertainty of the neutron signal in the typical state is equivalent to the establishment of a standard look-up table or a fitting curve, then the standard sample is adopted for calibrating the actual measurement neutron signal, and the standard neutron signal calibrated by the uncertainty required by the standard look-up table or the fitting curve and the actual measurement neutron signal are measured by adopting the same transmission line; this reduces errors, and the real-time construction of the standard look-up table or fitted curve advantageously eliminates environmental effects, which are consistent with the measured environment, and the two data remain consistent with the environment.
The actual measurement uncertainty evaluation refers to the uncertainty evaluation of the neutron signal obtained by the reactor in the actual environment, so that the uncertainty of the actual measurement neutron signal is obtained. The actual measurement uncertainty evaluation process is carried out relative to the actual measurement neutron signal obtained by the average method downsampling processing, specifically, the uncertainty of the neutron signal in a typical state can be adopted for calibrating the actual measurement neutron signal, and the actual measurement uncertainty evaluation process can also be directly obtained by calculating the uncertainty by adopting an uncertainty evaluation algorithm; the method comprises the following steps that the uncertainty of a neutron signal in a typical state is constructed, namely a standard look-up table or a fitting curve is constructed, then a measured neutron signal is calibrated by adopting a standard sample, and the standard neutron signal calibrated by the uncertainty required by the standard look-up table or the fitting curve and the measured neutron signal are measured by adopting the same transmission line; this reduces errors, and the real-time construction of the standard look-up table or fitted curve advantageously eliminates environmental effects, which are consistent with the measured environment, and the two data remain consistent with the environment.
Preferably, the method for determining uncertainty of the measured neutron signal by constructing the standard look-up table comprises the following steps:
s3, the actual measurement uncertainty evaluation specifically comprises the following steps:
s31, setting a neutron signal stabilizing source, measuring the neutron signals in X typical stable states, carrying out Y-time measurement in each typical stable state to obtain Y standard neutron signals, and carrying out uncertainty calculation on the Y standard neutron signals to obtain the uncertainty of the Y standard neutron signals;
s32, forming a standard uncertainty query table according to the uncertainty obtained in the S31;
s33, sampling the neutron signal sequence I with the frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn And substituting or interpolating the measured data into a standard uncertainty query table to obtain the table look-up uncertainty, and recording the table look-up uncertainty as the actual measurement uncertainty of the neutron signal sequence under different sampling frequencies.
Preferably, the method for determining uncertainty of the actually measured neutron signal by constructing the standard uncertainty curve comprises the following steps:
s3, the specific process of actual measurement uncertainty evaluation is as follows:
s31, setting a neutron signal stable source, measuring the neutron signals in X typical stable states, wherein Y times of measurement are carried out in each typical stable state to obtain Y standard neutron signals, and calculating the uncertainty of the Y standard neutron signals to obtain the uncertainty of the Y standard neutron signals;
s32, fitting according to the uncertainty obtained in the S31 to form a standard uncertainty curve;
s33, sampling the neutron signal sequence I with the frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn And substituting or interpolating the measured value into a standard uncertainty curve to obtain fitting uncertainty, and recording the fitting uncertainty as the measured uncertainty of the neutron signal sequence under different sampling frequencies.
In the step S31, uncertainty calculation is performed
The calculation is carried out in such a way that,
Preferably, the first and second liquid crystal materials are,
s2, the specific process of the elimination method down-sampling treatment is as follows:
taking a measured value of neutron signal data of a adjacent point positions as an equal gap length, and removing data points in the gap to obtain a neutron signal data measurement after down sampling; where a = pre-downsampling frequency/post-downsampling frequency.
The essence of down-sampling is to obtain new data sets after reducing sampling points, and reconstruct a plurality of new data sets under the same maximum frequency sampling environment. For example, assuming that the maximum sampling frequency is 1000Hz, assuming that the down-sampled frequency of 500Hz is the target, the sampling points are reduced by 1 time, and therefore, a is set to 2, wherein 1000 sampling points obtained by the maximum sampling frequency are sequentially ordered to form a sequence, the down-sampling process is to remove the 2 nd sampling point from the 1 st sampling point, the 2 nd sampling point, and the 3 rd sampling point, and so on, to obtain 500 sampling point data, and the 500 sampling point data form a new sequence.
Specifically, fmax is 1000Hz, f1 is 800Hz, and fn is 100Hz, which represents only one example thereof.
The process of neutron monitoring when the reactor is introduced with reactivity is as follows:
after the reactor is in a critical steady state for a certain time, introducing reactivity in a mode of adjusting the rod position of a control rod, and simultaneously measuring a neutron signal in the adjusting process by adopting a neutron detector; in the measuring process, an amplifier is adopted to amplify a measuring signal of the neutron detector, and the measuring signal is converted into a voltage signal and then transmitted to a data acquisition card with the maximum sampling frequency.
S5, the optimal judgment standard is as follows:
and 4, calculating the average value or weighted average value of the corrected and synthesized uncertainty of the neutron signal sequences obtained after the correction at different sampling frequencies, and selecting 1 group of neutron signal sequences with the lowest calculation result value as the optimal neutron signal sequence.
For subsequent reactivity calculations, the invention directly determines the data set with the best uncertainty as the basis for the subsequent measurement calculations.
The neutron signal sequences under different sampling frequencies respectively have: the neutron signal sequence If1 … with the sampling frequency f1 is the neutron signal sequence Ifn with the sampling frequency fn, wherein the neutron signal sequence If1 comprises sampling points: if1, 1..., if1, x, their corresponding corrected synthetic uncertainties comprise: uf1, 1.... U.1, x, wherein the subsignal sequence If1 has: (uf 1,1+.. + q. + xuf, X/X, or q. Uf1,1+.. + q. Xuf, X/X, were calculated, and the calculation result was denoted as uf1, and similarly, the sub-signal sequence Ifn has: the calculation result value is ufn; the optimal determination refers to comparing the sizes of uf1.. Ufn; and selecting the 1 group of neutron signal sequences with the lowest value as the optimal. And X is a sampling point in the corresponding group of neutron signal sequences. q is a weight.
Introducing a correction factor C (t) to a neutron signal sequence I with a sampling frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn Neutron signal data measured value I at middle t moment m,i (t) correcting to obtain corrected neutron signal data measured value I i (t)＝I m,i (t) C (t); the correction factor C (t) is the correction factor of the signal at the t sampling moment;
uncertainty u [ C (t) ] incorporating a correction factor]For neutron signal sequence I with sampling frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn Synthesizing the actual measurement uncertainty to obtain corrected synthesis uncertainty of the corrected neutron signal data measured value;
u[I m,i (t)]is I m,i (t) measured uncertainty.
The invention has the following effects: aiming at the influence of factors such as neutron signal statistical fluctuation, high-voltage ripples, electromagnetic interference and the like in the reactivity measurement process, the nuclear reactor reactivity measurement method capable of reducing the influence is established. By adopting a mathematical algorithm based on uncertainty analysis, the uncertainty of neutron signal measurement is reduced, the uncertainty introduced by a correction factor is reduced, and the efficiency and the accuracy of reactivity measurement are improved.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
FIG. 1 is a schematic flow chart of a reactivity measurement method based on correction signal optimization processing.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
Example 1
As shown in fig. 1:
s1, maximum frequency sampling processing: when the reactor is introduced with reactivity, neutron signal monitoring is carried out, and neutron signal sampling is carried out by adopting a data acquisition card with the maximum sampling frequency; a group of neutron signal sequences I with the maximum sampling frequency fmax output by the data acquisition card fmax (ii) a The neutron signal sequence I fmax Includes I neutron signal data measured values, I 1 、I 2 、…I i (ii) a i represents a sampling point, and the size of i is determined according to fmax;
s2, eliminating the method and carrying out down-sampling treatment: partial data point pair neutron signal sequence I is eliminated by adopting equal intervals fmax Performing down-sampling processing for n times to obtain a neutron signal sequence I with the sampling frequency of f1 f1 … neutron signal sequence I with sampling frequency fn fn (ii) a f1 and fn are both smaller than fmax;
s3, evaluating the actually measured uncertainty: for neutron signal sequence I with sampling frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn Carrying out actual measurement uncertainty evaluation to obtain actual measurement uncertainty of the neutron signal sequence under different sampling frequencies;
s4, correcting: neutron signal sequence I with correction factor to sampling frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn Correcting to obtain a corrected neutron signal sequence; correction factor-introduced uncertainty versus neutron signal sequence I with sampling frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn Carrying out uncertainty synthesis on the actual measurement uncertainty to obtain corrected synthesis uncertainty of the corrected neutron signal sequence;
s5, optimal judgment: according to the neutron signal sequence I with the corrected sampling frequency of f1 f1 Corrected synthetic uncertainty … neutron signal sequence I with sampling frequency fn fn The corrected synthesis uncertainty is subjected to optimal judgment, a corrected signal data set with the optimal uncertainty is selected from the corrected synthesis uncertainty, and a neutron signal sequence corresponding to the optimal uncertainty is recorded as an optimal neutron signal sequence;
s6, reactivity analysis: and performing reactivity measurement calculation analysis by adopting the optimal neutron signal sequence to obtain a reactivity measurement result, and synthesizing the uncertainty of the optimal neutron signal sequence to obtain the uncertainty corresponding to the reactivity measurement result.
The invention firstly adopts the maximum frequency to sample, thus enough data points can be obtained by one-time sampling, then the elimination method is adopted to carry out down-sampling treatment to form different data groups, thus the data groups with different frequencies under the same sampling environment can be directly obtained, the external environments of the data groups are the same, the traditional method is repeated sampling times, and in each sampling, because the influences of factors such as neutron signal statistical fluctuation, high-voltage ripple waves, electromagnetic interference and the like in the measurement process of different times are different, the data sampled in each time are not completed under the same environment, and the final reactive error can be increased.
The actual measurement uncertainty evaluation refers to the uncertainty evaluation of the neutron signal obtained by the reactor in the actual environment, so that the uncertainty of the actual measurement neutron signal is obtained. The actual measurement uncertainty evaluation process is carried out relative to the elimination method for reducing the sampling processing of the obtained actual measurement neutron signal, and specifically, the uncertainty of the neutron signal in a typical state can be adopted for calibrating the neutron signal, wherein the establishment of the uncertainty of the neutron signal in the typical state is equivalent to the establishment of a standard look-up table or a fitting curve, then the standard sample is adopted for calibrating the actual measurement neutron signal, and the standard neutron signal calibrated by the uncertainty required by the standard look-up table or the fitting curve and the actual measurement neutron signal are measured by adopting the same transmission line; this reduces errors, and the real-time construction of the standard look-up table or fitted curve advantageously eliminates environmental effects, which are consistent with the measured environment, and the two data remain consistent with the environment.
Example 2
As shown in fig. 1:
on the basis of the above embodiment 1, the method for determining uncertainty of an actually measured neutron signal by constructing a standard look-up table includes:
s3, the specific process of actual measurement uncertainty evaluation is as follows:
s31, setting a neutron signal stable source, measuring neutron signals in X typical stable states, carrying out Y-time measurement in each typical stable state to obtain Y standard neutron signals, and carrying out uncertainty calculation on the Y standard neutron signals to obtain uncertainty of the Y standard neutron signals;
s32, forming a standard uncertainty query table according to the uncertainty obtained in the S31;
s33, sampling the neutron signal sequence I with the frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn Substituting or interpolating into a standard uncertainty query table to obtain the table look-up uncertainty, and recording the table look-up uncertainty as the actual measurement uncertainty of the neutron signal sequence under different sampling frequencies.
Example 3
As shown in fig. 1:
on the basis of the above embodiment 1, the method for determining uncertainty of an actually measured neutron signal by constructing a standard uncertainty curve is as follows:
s3, the specific process of actual measurement uncertainty evaluation is as follows:
s31, setting a neutron signal stabilizing source, measuring the neutron signals in X typical stable states, carrying out Y-time measurement in each typical stable state to obtain Y standard neutron signals, and carrying out uncertainty calculation on the Y standard neutron signals to obtain the uncertainty of the Y standard neutron signals;
s32, fitting according to the uncertainty obtained in the S31 to form a standard uncertainty curve;
s33, sampling the neutron signal sequence I with the frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn And substituting or interpolating the measured value into a standard uncertainty curve to obtain fitting uncertainty, and recording the fitting uncertainty as the measured uncertainty of the neutron signal sequence under different sampling frequencies.
In the step S31, uncertainty calculation is performed
The calculation is carried out in such a way that,
Preferably, the first and second liquid crystal materials are,
s2, the specific process of the elimination method down-sampling treatment is as follows:
taking a measured value of neutron signal data of adjacent point positions as an equal gap length, and removing data points in the gap to obtain a neutron signal data measurement after down sampling; where a = pre-downsampling frequency/post-downsampling frequency.
The essence of down-sampling is to reduce the number of samples to obtain a new data set, and reconstruct multiple new data sets in the same maximum frequency sampling environment. For example, assuming that the maximum sampling frequency is 1000Hz, assuming that the down-sampled frequency of 500Hz is the target, the sampling point is reduced by 1 time, and therefore, a is set to 2, wherein 1000 sampling points obtained by the maximum sampling frequency are sequentially ordered to form a sequence, the down-sampling process is to remove the 1 st sampling point, the 2 nd sampling point, and the 2 rd sampling point in the 3 rd sampling point, and so on, to obtain 500 sampling point data, and the 500 sampling point data form a new sequence.
Example 4
As shown in fig. 1:
specifically, fmax is 1000Hz, f1 is 800Hz, and fn is 100Hz, which represents only one example thereof.
The process of neutron monitoring when the reactor is introduced with reactivity is as follows:
after the reactor is in a critical steady state for a certain time, introducing reactivity by adjusting the rod position of a control rod, and simultaneously measuring a neutron signal in the adjusting process by adopting a neutron detector; in the measuring process, an amplifier is adopted to amplify a measuring signal of the neutron detector, and the measuring signal is converted into a voltage signal and then transmitted to a data acquisition card with the maximum sampling frequency.
S5, the optimal judgment standard is as follows:
and (5) calculating the average value or weighted average value of the corrected and synthesized uncertainties of the neutron signal sequences under different sampling frequencies obtained after the correction in the step (S4), and selecting 1 group of neutron signal sequences with the lowest calculation result value as the optimal neutron signal sequence.
For subsequent reactivity calculations, the present invention directly determines the data set with the best uncertainty as the basis for subsequent measurement calculations.
The neutron signal sequences under different sampling frequencies respectively have: the neutron signal sequence If1 … with the sampling frequency f1 is the neutron signal sequence Ifn with the sampling frequency fn, wherein the neutron signal sequence If1 comprises sampling points: if1, if1, x, their corresponding corrected synthetic uncertainties include: uf1, uf1, x, wherein the subsignal sequence If1 has: (uf 1,1+.. + q. + xuf, X/X, or q. Uf1,1+.. + q. Xuf, X/X, were calculated, and the calculation result was denoted as uf1, and similarly, the sub-signal sequence Ifn has: the calculation result value is ufn; the optimal decision is to compare the sizes of uf1.... Ufn; and selecting the 1 group of neutron signal sequences with the lowest value as the optimal. And X is a sampling point in the corresponding group of neutron signal sequences. q is a weight.
Introducing a correction factor C (t) to a neutron signal sequence I with a sampling frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn Neutron signal data measured value I at middle t moment m,i (t) correcting to obtain corrected neutron signal data measured value I i (t)＝I m,i (t) C (t); the correction factor C (t) is the correction factor of the signal at the t sampling moment;
uncertainty u [ C (t) ] incorporating correction factors]For neutron signal sequence I with sampling frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn Synthesizing the actual measurement uncertainty to obtain corrected synthesis uncertainty of the corrected neutron signal data measured value;
u[I m,i (t)]is I m,i (t) measured uncertainty.
For reactivity, a final reactivity measurement result can be obtained by combining the corrected reactivity measurement neutron signal obtained by the method and the uncertainty thereof with a reactivity measurement formula; and based on standard uncertainty synthesis algorithm or other approximate uncertainty synthesis algorithm specified by the laws and regulations, performing uncertainty synthesis to obtain the uncertainty of the method.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (10)
1. A reactivity measurement method based on correction signal optimization processing is characterized by comprising the following steps:
s1, maximum frequency sampling processing: when the reactor is introduced with reactivity, neutron signal monitoring is carried out, and neutron signal sampling is carried out by adopting a data acquisition card with the maximum sampling frequency; a group of neutron signal sequences I with the maximum sampling frequency fmax output by the data acquisition card fmax (ii) a The neutron signal sequence I fmax Includes I neutron signal data measured values, I 1 、I 2 、…I i (ii) a i represents a sampling point, and the size of i is determined according to fmax;
s2, removing the down-sampling processing by a method: partial data point pair neutron signal sequence I is eliminated by adopting equal intervals fmax Performing down-sampling processing for n times to obtain a neutron signal sequence I with the sampling frequency of f1 f1 … neutron signal sequence I with sampling frequency fn fn (ii) a f1 and fn are both smaller than fmax;
s3, evaluating the actually measured uncertainty: for neutron signal sequence I with sampling frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn Carrying out actual measurement uncertainty evaluation to obtain actual measurement uncertainty of the neutron signal sequence under different sampling frequencies;
s4, correcting: neutron signal sequence I with correction factor to sampling frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn Correcting to obtain a corrected neutron signal sequence; correction factor-introduced uncertainty versus sampling frequency f1 neutron signal sequence I f1 … neutron signal sequence I with sampling frequency fn fn Carrying out uncertainty synthesis on the actual measurement uncertainty to obtain corrected synthesis uncertainty of the corrected neutron signal sequence;
s5, optimal judgment: according to the neutron signal sequence I with the corrected sampling frequency of f1 f1 Corrected synthetic uncertainty … neutron signal sequence I with sampling frequency fn fn The corrected synthesis uncertainty is subjected to optimal judgment, a corrected signal data set with the optimal uncertainty is selected from the corrected synthesis uncertainty, and a neutron signal sequence corresponding to the optimal uncertainty is recorded as an optimal neutron signal sequence;
s6, reactivity analysis: and performing reactivity measurement calculation analysis by adopting the optimal neutron signal sequence to obtain a reactivity measurement result, and synthesizing the uncertainty of the optimal neutron signal sequence to obtain the uncertainty corresponding to the reactivity measurement result.
2. The reactivity measurement method based on modified signal optimization process according to claim 1,
s3, the specific process of actual measurement uncertainty evaluation is as follows:
s31, setting a neutron signal stabilizing source, measuring the neutron signals in X typical stable states, wherein Y times of measurement are carried out in each typical stable state to obtain Y standard neutron signals, and uncertainty calculation is carried out on the Y standard neutron signals in each typical stable state to obtain corresponding uncertainty of the Y standard neutron signals in each typical stable state, so that X uncertainties corresponding to the Y standard neutron signals in the X typical stable states are obtained;
s32, forming a standard uncertainty query table according to the X uncertainties obtained in the S31;
s33, sampling the neutron signal sequence I with the frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn Substituting the measured neutron signal sequence into a standard uncertainty query table to obtain the table look-up uncertainty, and recording the table look-up uncertainty as the measured neutron signal sequence uncertainty under different sampling frequencies.
3. The reactivity measurement method based on modified signal optimization process according to claim 1,
s3, the specific process of actual measurement uncertainty evaluation is as follows:
s31, setting a neutron signal stable source, measuring the neutron signals in X typical stable states, wherein Y times of measurement are carried out in each typical stable state to obtain Y standard neutron signals, and calculating the uncertainty of the Y standard neutron signals in each typical stable state to obtain the corresponding uncertainty of the Y standard neutron signals in each typical stable state, so that X uncertainties corresponding to the Y standard neutron signals in the X typical stable states are obtained;
s32, fitting and forming a standard uncertainty curve according to the X uncertainties obtained in the S31;
s33, sampling the neutron signal sequence I with the frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn Substituting into standard uncertainty curve to obtain uncertainty of fittingAnd degree, and the fitting uncertainty is recorded as the actual measurement uncertainty of the neutron signal sequence under different sampling frequencies.
4. The reactivity measurement method based on modified signal optimization process according to claim 2 or 3,
in S31, uncertainty calculation is performed
The calculation is carried out in such a way that,
5. A reactivity measurement method based on modified signal optimization processing according to claim 2 or 3,
s2, the specific process of the elimination method down-sampling treatment is as follows:
taking a measured value of neutron signal data of a adjacent point positions as an equal gap length, and removing data points in the gap to obtain a neutron signal data measurement after down sampling; where a = pre-downsampling frequency/post-downsampling frequency.
6. The reactivity measurement method based on modified signal optimization process according to claim 1,
fmax is 1000Hz, f1 is 800Hz, fn is 100Hz.
7. The reactivity measurement method based on modified signal optimization process according to claim 1,
the process of neutron monitoring when the reactor is introduced with reactivity is as follows:
after the reactor is in a critical steady state for a certain time, introducing reactivity by adjusting the rod position of the control rod, and simultaneously measuring a neutron signal in the rod position adjusting process of the control rod by adopting a neutron detector; in the measuring process, an amplifier is adopted to amplify a measuring signal of the neutron detector, and the measuring signal is converted into a voltage signal and then transmitted to a data acquisition card with the maximum sampling frequency.
8. The reactivity measurement method based on modified signal optimization process according to claim 1,
s5, the optimal judgment standard is as follows:
and 4, calculating the average value or weighted average value of the corrected and synthesized uncertainty of the neutron signal sequences obtained after the correction at different sampling frequencies, and selecting 1 group of neutron signal sequences with the lowest calculation result value as the optimal neutron signal sequence.
9. The reactivity measurement method based on modified signal optimization process according to claim 8,
the neutron signal sequences under different sampling frequencies respectively have: neutron signal sequence I with sampling frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn Neutron signal sequence I f1 The method comprises the following sampling points: I.C. A f1，1 、.....、I f1，x The corresponding corrected composite uncertainty includes: u. of f1，1 、.....、u f1，x Wherein the sub-signal sequence I f1 Comprises the following steps: (u) f1，1 +....+u f1，x ) (ii)/X or q #u f1，1 +....+q*xu f1，x Calculating by the aid of the/X, and recording the calculation result value as u f1 In the same way, wherein the sub-signal sequence I fn Comprises the following steps: the calculation result value is recorded as u fn (ii) a Optimal decision rule refers to comparison u f1 .....u fn The size of (d); selecting 1 group of neutron signal sequences with the lowest value as the optimal; x is a sampling point in the corresponding group of neutron signal sequences; q is a weight.
10. The reactivity measurement method based on modified signal optimization process according to claim 1,
introducing a correction factor C (t) to a neutron signal sequence I with a sampling frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn Neutron signal data measured value I at middle t moment m,i (t) correcting to obtain corrected neutron signal data measured value I i (t)＝I m,i (t) C (t); the correction factor C (t) is the correction factor of the signal at the t sampling moment;
uncertainty u [ C (t) ] incorporating a correction factor]For neutron signal sequence I with sampling frequency f1 f1 … neutron signal sequence I with sampling frequency fn fn Synthesizing the actual measurement uncertainty to obtain corrected synthesis uncertainty of the corrected neutron signal data measured value;
u[I m,i (t)]is I m,i (t) measured uncertainty.
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