CN109117591B - Dynamic reactivity measuring method based on multi-detector measuring signals - Google Patents
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Abstract
The invention discloses a dynamic reactivity measuring method based on multi-detector measuring signals, aiming at the defects of the existing single-detector point stack model, the invention establishes a reactor dynamic reactivity measuring method capable of eliminating the error of the rod drop reactivity space effect measured by the point stack model by performing coupling analysis on the measuring signals of a plurality of detectors through three-dimensional space-time dynamics analysis. The method adopts the method of calculating physical parameters based on three-dimensional space-time dynamics analysis and combining with a three-dimensional physical model, couples measurement signals of multiple detectors, is used for reactivity measurement, improves the defects of the original measurement method, and improves the accuracy of a dynamic reactivity measurement result.
Description
Technical Field
The invention relates to the field of reactor dynamic reactivity measurement, in particular to a dynamic reactivity measurement method based on multi-detector measurement signals.
Background
The dynamic 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 currently common method for measuring the large reactivity is a rod dropping method, and 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, and the quick measurement of large reactivity such as control rod integral value, rod clamping subcritical degree and shutdown depth can be realized.
Most of the measurement methods are generally based on a point reactor model, a single detector is adopted for measuring the reactivity, the measurement process is easily influenced by a neutron flux space effect, and the reactivity measurement result has errors. The dynamic rod carving method is combined with three-dimensional physical calculation analysis, so that the space effect in the measuring process is reduced, and the measuring error cannot be completely eliminated.
Neutron signals are measured by adopting multi-detector array coupling, the measured signals are coupled based on three-dimensional space-time dynamics analysis, and dynamic reactivity is measured, so that the space effect of a single detector in the measuring process is further reduced, and a more accurate dynamic reactivity measuring result is obtained.
Several studies have been conducted internationally on dynamic measurements of reactivity. In 1989, glumac et al put forward a method for measuring the value of a control rod of a rapid rod insertion so as to meet the requirement of a nuclear power station on rapid measurement of the value of the control rod. In 1992, zhao Rong' an et al, west House, proposed a dynamic rod-carving method (DRWM) which inserts control rods at maximum speed, performs physical calculation correction by combining three-dimensional space-time dynamics analysis, measures the micro-integral value of control rods of a commercial reactor, and is widely applied to various nuclear power stations. On this basis, e.k.lee et al in korea conducted similar studies based on the CE System80 stack type. The russian developed a revised inverse dynamic method measurement study in 2010. However, at present, few dynamic reactivity measurement studies based on multi-detector measurement signals exist abroad.
However, in China, research institutions develop correction calculation research based on three-dimensional physical analysis aiming at the dynamic rod carving technology, and research institutions also perform correction research aiming at the reactivity measurement process of a single-detector inverse dynamic method, but there is no report that the unit performs research on a multi-detector measurement signal coupling method for dynamic reactivity measurement or applies for related patent technologies based on three-dimensional space-time dynamic analysis. Therefore, it is necessary to master a dynamic reactivity measurement method based on multiple detector measurement signals to provide an ability to accurately measure dynamic reactivity, in view of the shortcomings of the existing single detector dynamic reactivity measurement method.
Disclosure of Invention
The invention provides a dynamic reactivity measuring method based on multi-detector measuring signals, which can improve the defects of a point pile model in the original single-detector measurement and obtain a more accurate dynamic reactivity measuring result.
The invention is realized by the following technical scheme:
a method for dynamic reactivity measurement based on multi-probe measurement signals, the method comprising the steps of:
firstly, collecting measurement signals at different positions inside or outside a reactor by adopting a plurality of neutron detectors;
step two, based on three-dimensional space-time dynamics analysis, calculating and simulating the actual measurement process to obtain a neutron flux shape function psi at the detector at each moment in the n-th detector dynamic measurement process c (t) measurement signals for the nth detectorPerforming primary treatment to obtain N n (t); the measuring signals of all the detectors are subjected to primary processing to obtain signals N of N detectors 1 (t)…N n (t);
Step three, signals N of N detectors 1 (t)…N n (t) carrying out coupling processing after normalization processing to obtain a detector coupling signal N (t);
and step four, performing dynamic reactivity calculation based on the detector coupling signal N (t) obtained in the step three.
Preferably, the specific process of the step one is as follows: lifting the control rods according to a rod lifting program to enable the reactor to reach a critical state, adjusting the power of the reactor, stabilizing the power at a certain level, enabling the current level of the out-of-reactor neutron detector to meet the measurement requirement, stabilizing for 3min, dropping the control rods to be measured into the reactor core, and acquiring neutron signals and rod position signals for moving the control rods.
Preferably, the second step is specifically: three-dimensional space-time dynamics computational analysis is carried out by adopting Monte Carlo method analysis software of a high-fidelity model, and a neutron flux shape function psi at a detector is directly obtained n (t)。
Preferably, the second step is specifically: calculating response functions of each position of the reactor core on the neutron flux contribution of the detector outside the reactor by adopting Monte Carlo method analysis software based on a high-fidelity model, calculating neutron flux shape function psi at the detector by combining absolute neutron flux distribution in the reactor obtained by a three-dimensional space-time dynamics analysis program n (t)。
Preferably, in the second step, the nth detector is measured byPerforming primary treatment to obtain N n (t):
Preferably, the signals N of the N detectors in the third step 1 (t)…N n (t) normalization processing to obtain normalized detection signal
Coupling the normalized signals of the N detectors by adopting an equal-weight coupling method, and obtaining a detector coupling signal N (t) according to the following formula:
preferably, the signals N of the N detectors in the third step 1 (t)…N n (t) normalization processing to obtain normalized detection signal
And coupling the normalized signals of the N detectors by adopting a weighted coupling method, and obtaining a detector coupling signal N (t) by the following formula:
wherein, W i : signal coupling weight factor W of ith detector i 。
Preferably, the dynamic reactivity calculation is performed in the fourth step by using the following formula:
for a measurement process that uses a proportional counter to measure a neutron count rate signal having a relatively low signal level, the dynamic reactivity measurement ρ is:
in the formula, k c The neutron effective value-added coefficient is in a stable state at the end of rod dropping; beta is a i The fraction of delayed neutrons of the ith group; lambda i Is the attenuation constant of the ith group of delayed neutrons;
for a measurement process that employs a neutron ionization chamber to measure a neutron current signal having a relatively high signal level, the dynamic reactivity measurement ρ (t) is:
in the formula, Λ is the time of the middle filial generation; beta is the effective share of delayed neutrons; beta is a i The fraction of delayed neutrons of the ith group; lambda [ alpha ] i Attenuation of delayed neutrons for the ith groupAnd (4) counting.
The invention has the following advantages and beneficial effects:
aiming at the defect that the existing reactor dynamic reactivity measurement method is based on a single-detector point reactor model, measurement signals of multiple detectors are coupled through three-dimensional calculation analysis, and the reactor dynamic reactivity measurement method capable of further reducing the error of the point reactor model in measuring the spatial effect of the reactivity is established. The physical parameters calculated based on the three-dimensional physical model are coupled with the measurement signals of the multiple detectors and used for measuring the reactivity, so that the defects of the original measurement method are overcome, and the accuracy and the reliability of the dynamic reactivity measurement result are improved.
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 the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not used as limiting the present invention.
Examples
The specific implementation process of the dynamic reactivity measurement method based on the multi-detector measurement signals comprises the following steps:
1. multiple detector measurement signal acquisition during measurement
A plurality of neutron detectors are adopted to acquire measurement signals at different positions inside or outside the reactor.
And lifting the control rods according to the rod lifting program to ensure that the reactor reaches critical, adjusting the power of the reactor, stabilizing the power at a certain level, ensuring that the current level of the out-of-reactor neutron detector meets the measurement requirement, stabilizing for 3min, enabling the control rod(s) to be detected to fall into the reactor core, and simultaneously acquiring neutron signals and rod position signals of the movable control rods.
2. Measurement signal processing and coupling
Based on three-dimensional space-time dynamics analysis, the actual measurement process is calculated and simulated to obtain the neutron flux shape function psi at the detector at each moment in the n-th detector dynamic measurement process n (t) and obtaining the neutron effective value-added system under the steady state of the rod-dropping end stateNumber k c . Monte Carlo method analysis software based on high fidelity model can be adopted to carry out three-dimensional space-time dynamics calculation analysis, and the shape function psi at the detector can be directly obtained n (t); or calculating the response function of each position of the reactor core contributing to the neutron flux at the detector outside the reactor by adopting analysis software based on a high fidelity model, obtaining the neutron flux distribution in the reactor by combining with a three-dimensional space-time dynamics analysis program, and calculating the neutron flux shape function psi at the detector n (t) of (d). Measuring the signal for the nth detector byCarrying out preliminary optimization to obtain N n (t) for subsequent coupling measurement analysis.
In order to further reduce the space effect caused by the position difference of the detectors, the method couples the signals of the detectors for subsequent analysis.
Because the positions of the detectors are different, the overall amplitude of the measured current signals at each time point is different, and therefore normalization processing needs to be performed on the signals of different detectors. Respectively normalizing the measurement signals of the n detectors, normalizing the measurement signals in the whole measurement process by taking the progressive steady-state signal value before rod drop as a reference to obtain the normalized measurement signals of the detectors
Then, the detector signals are coupled by adopting an equal weight coupling method or a weighted coupling method:
the equal weight coupling method comprises the following steps: directly coupling the normalized signals of the N detectors, and obtaining a coupled detector signal N (t) according to the following formula;
weighted even sum method: processing factor based on individual detector measurement signalsDegree of deviation σ from 1 i (the integral deviation or the maximum deviation can be used as the deviation measure) according to the i Based on a certain algorithm, obtaining a signal coupling weight factor W of the detector i =f(σ i ) (degree of deviation σ) i The larger the detector coupling factor), the signals to all detectorsCoupling is performed and the coupled detector signal N (t) is derived from the following equation.
3. Dynamic reactivity calculation
Performing dynamic reactivity calculation based on the detector coupling signals obtained in the above items 2 and 1 by using the following formula:
for a measurement process that a proportional counter tube is adopted to measure a neutron count rate signal with a relatively low signal level, a dynamic reactivity measured value rho is as follows:
in the formula, k c The neutron effective value-added coefficient is in a stable state at the end of rod dropping; beta is a i The fraction of delayed neutrons of the ith group; lambda [ alpha ] i And calculating the attenuation constant of the ith group of delayed neutrons by physical calculation software or other calculation methods.
For a measurement process that employs a neutron ionization chamber to measure a neutron current signal having a relatively high signal level, the dynamic reactivity measurement ρ (t) is:
in the formula, the filial generation time in the lambda; beta is effective share of delayed neutrons; beta is a i The fraction of delayed neutrons of the ith group; lambda [ alpha ] i And calculating the attenuation constant of the ith group of delayed neutrons by physical calculation software or other calculation methods.
The above-mentioned embodiments, objects, technical solutions and advantages of the present invention are further described in detail, it should be understood that the above-mentioned embodiments are only examples 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 (8)
1. A method for dynamic reactivity measurement based on multi-probe measurement signals, the method comprising the steps of:
firstly, collecting measurement signals at different positions inside or outside a reactor by adopting a plurality of neutron detectors;
step two, based on three-dimensional space-time dynamics analysis, calculating and simulating the actual measurement process to obtain a neutron flux shape function psi at the detector at each moment in the n-th detector dynamic measurement process c (t) measurement signals for the nth detectorPerforming primary treatment to obtain N n (t); the measuring signals of all the detectors are subjected to primary processing to obtain signals N of N detectors 1 (t)…N n (t);
Step three, signals N of N detectors 1 (t)…N n (t) carrying out coupling processing after normalization processing to obtain a detector coupling signal N (t);
and step four, performing dynamic reactivity calculation based on the detector coupling signal N (t) obtained in the step three.
2. The method for measuring the dynamic reactivity based on the multi-detector measuring signals according to claim 1, wherein the steps are specifically as follows: and lifting the control rods according to the rod lifting program to ensure that the reactor reaches critical, adjusting the power of the reactor, stabilizing the power at a certain level, ensuring that the current level of the out-of-reactor neutron detector meets the measurement requirement, stabilizing for 3min, dropping the control rods to be detected into the reactor core, and simultaneously acquiring neutron signals and rod position signals of the movable control rods.
3. The method for measuring dynamic reactivity according to claim 1, wherein the second step is to: three-dimensional space-time dynamics computational analysis is carried out by adopting Monte Carlo method analysis software of a high-fidelity model, and a neutron flux shape function psi at a detector is directly obtained n (t)。
4. The method for measuring dynamic reactivity according to claim 1, wherein the second step is to: calculating response functions of each position of the reactor core on the neutron flux contribution of the detector outside the reactor by adopting Monte Carlo method analysis software based on a high-fidelity model, calculating neutron flux shape function psi at the detector by combining absolute neutron flux distribution in the reactor obtained by a three-dimensional space-time dynamics analysis program n (t)。
6. Method according to claim 5, wherein the signal N of N detectors in the third step is measured 1 (t)…N n (t) normalization processing to obtain normalized detection signal
Coupling the normalized signals of the N detectors by adopting an equal-weight coupling method, and obtaining a detector coupling signal N (t) according to the following formula:
7. the method as claimed in claim 5, wherein the signal N of N detectors in the third step is used as the signal of N detectors 1 (t)…N n (t) normalization processing to obtain normalized detection signal
And coupling the normalized signals of the N detectors by adopting a weighted coupling method, and obtaining a detector coupling signal N (t) by the following formula:
wherein, W i : signal coupling weight factor W of ith detector i 。
8. The method for measuring dynamic reactivity based on multi-detector measurement signals according to claim 1, wherein the dynamic reactivity calculation is performed in the fourth step by using the following formula:
for a measurement process that a proportional counter tube is adopted to measure a neutron count rate signal with a relatively low signal level, a dynamic reactivity measured value rho is as follows:
in the formula, k c The neutron effective value-added coefficient is in a stable state at the end of rod dropping; beta is a i The fraction of delayed neutrons of the ith group; lambda i Is the attenuation constant of the ith group of delayed neutrons;
for a measurement process that employs a neutron ionization chamber to measure a neutron current signal having a relatively high signal level, the dynamic reactivity measurement ρ (t) is:
in the formula, Λ is the time of the middle filial generation; beta is effective share of delayed neutrons; beta is a beta i The fraction of delayed neutrons of the ith group; lambda [ alpha ] i Is the attenuation constant of the ith group of delayed neutrons.
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CN112687411B (en) * | 2020-12-24 | 2022-06-24 | 中国核动力研究设计院 | Reactivity measurement method based on multi-detector relay signals |
CN113161028B (en) * | 2021-03-19 | 2023-01-24 | 中国核动力研究设计院 | Reactivity measurement method based on correction signal optimization processing |
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Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
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JP2004279338A (en) * | 2003-03-18 | 2004-10-07 | Tokyo Electric Power Co Inc:The | Method for measuring temperature reactivity coefficient of nuclear reactor |
CN104934083A (en) * | 2015-04-27 | 2015-09-23 | 中国原子能科学研究院 | Method for measuring effective share of delayed neutrons |
CN106898394A (en) * | 2017-03-31 | 2017-06-27 | 中国核动力研究设计院 | A kind of measurement of rod worth method of WWER hexagonal lattices reactor core |
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US4877575A (en) * | 1988-01-19 | 1989-10-31 | Westinghouse Electric Corp. | Core reactivity validation computer and method |
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Patent Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2004279338A (en) * | 2003-03-18 | 2004-10-07 | Tokyo Electric Power Co Inc:The | Method for measuring temperature reactivity coefficient of nuclear reactor |
CN104934083A (en) * | 2015-04-27 | 2015-09-23 | 中国原子能科学研究院 | Method for measuring effective share of delayed neutrons |
CN106898394A (en) * | 2017-03-31 | 2017-06-27 | 中国核动力研究设计院 | A kind of measurement of rod worth method of WWER hexagonal lattices reactor core |
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Title |
---|
随机中子动力学及其数值模拟研究进展;杨俊云等;《计算物理》;20170325;第34卷(第02期);第127-141页 * |
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