CN107230505A - A kind of reactor nucleus power monitoring method and system - Google Patents
A kind of reactor nucleus power monitoring method and system Download PDFInfo
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- CN107230505A CN107230505A CN201710475532.4A CN201710475532A CN107230505A CN 107230505 A CN107230505 A CN 107230505A CN 201710475532 A CN201710475532 A CN 201710475532A CN 107230505 A CN107230505 A CN 107230505A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/104—Measuring reactivity
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Abstract
The invention discloses a kind of reactor nucleus power monitoring method and system, its method includes A, after reactor power level is stable, and the neutronic noise signal of reactor is measured using two neutron being arranged symmetrically gamma compensated ionization chambers；B, the FFT to two groups of neutronic noise signal of change time signals, calculate cross-spectral density φXYAnd normalized；C, cross-spectral density is fitted, and calculates frequencies omega1When cross-spectral density φXY(ω1)；D, the parameter obtained according to fitting, obtain reactor fission rate F, so as to obtain reactor absolute power P.It carries out parameter measurement under not disturbing reaction heap normally operation, it is adaptable to all reactors, and measurement is convenient and quick.
Description
Technical field
Field is monitored the present invention relates to reactor nucleus power, and in particular to one kind is reacted based on neutronic noise signal come scale
Core power monitor method and system.
Background technology
In reactor zero power physics testing, to ensure that operation power is no more than related nuclear safety codes and operation limit
The requirement of value and condition, while also providing input parameter to check theoretical calculation, needs the absolute power of knowing reaction heap.
In thermal neutron zero power reactor, scale absolute power generally uses activation analysis, and this method modifying factor is very
Many, data processing is also more complicated, for swimming pool reactor or zero-energy reactor, because the arrangement of active region often changes,
The absolute power of reactor is measured, just necessary often scale, it appears fairly cumbersome.Also one kind is passed in and out according to reactor coolant
Mouthful temperature difference and total flow are come the method that calculates absolute power, but it is only applicable to the higher power reactor of power.It is anti-for low-power
Answer heap or the temperature difference is small, system radiating amount very big swimming pool reactor, the absolute power error determined in this way is very big.Other sides
Method such as source introduction method, due to neutron source active strength dyscalculia, there is uncertainty in neutron source reactivity worth, therefore, survey
Measure result less reliable.
The content of the invention
In order to solve the above-mentioned technical problem the present invention provides a kind of reactor nucleus power monitoring method and system, and it is not being done
Disturb and parameter measurement is carried out under normal reactor operation, it is adaptable to all reactors, measurement is convenient and quick.
The present invention is achieved through the following technical solutions：
A kind of reactor nucleus power monitoring method, comprises the following steps：
A, after reactor is stable up to critical power level, in order to which the space for reducing reactor in-core neutron flux is imitated
Should, the neutronic noise signal of reactor is measured using two neutron being arranged symmetrically gamma compensated ionization chambers；
B, the FFT to two groups of neutronic noise signal of change time signals, calculate cross-spectral density φXYAnd at normalization
Reason；
C, cross-spectral density is fitted, obtains cross-spectral density matched curve, frequency is obtained in matched curve
Rate ω1When cross-spectral density φ 'XY(ω1)；
D, the parameter obtained according to fitting, obtain reactor fission rate F, so as to obtain reactor absolute power P.
The method part of this programme includes pile neutron noise signal measuring process and power measurement step, wherein, step
Rapid B, C, D belong to power measurement step, obtain cross-spectral density by neutron noise signal analyze and are fitted
To dynamic parameter, so as to obtain absolute power.Measured and obtained under not disturbing reaction heap normally operation using the data of this method,
Suitable for all reactors, it is not necessary to which frequent scale, measurement is convenient and quick, and its measurement accuracy is high, effectively solve existing
There is the problems such as error is greatly in low-power reactor power measurement and process is numerous and diverse.
Preferably, in step B, in addition to the smoothing processing of cross-spectral density, the number of times of the smoothing processing is big
In equal to 8 times.Cross-spectral density is smoothed, the interference of random noise, the number of times of smoothing processing can be effectively reduced
At 8 times, the influence of random noise can be excluded or reduced substantially.
Further, the method for the smoothing processing is specially：Current cross-spectral density was effectively measured with last time
Calculate obtained cross-spectral density to be averaged, obtain the average cross-spectral density of two groups of noise signals, and draw mutual work(
Rate spectrum density curve.
Preferably, cross-spectral density φ ' after normalizationXYFor：
Wherein, A is related to reactor power level, ionisation chamber detection efficient normal
Number；β is effective delayed neutron fraction；ω is angular frequency；ι is prompt neutron removal lifetime；
Further, step C is fitted using nonlinear least square method, is specially：Using non-linear least square
Method fitting parameter input parameter A, ι, β fitting initial value, the installation warrants reactor core physical theory of initial value, which is calculated, to be obtained
The dynamic parameter value obtained is configured, and obtains Reactor dynamic parameters A, ι, β of fitting.
Preferably, in the step D, reactor fission rate F is：
Wherein, D refers to driven factor, and β is effective delayed neutron fraction；
Reactor absolute power P is：P=P0F, wherein, P0Refer to the energy that a nuclear fission is discharged.
The measuring method be using the average current or the statistic fluctuation of voltage caused by a large amount of neutrons as Fundamentals of Measurement,
Further according to the output signal of reactor Reactor dynamic parameters are determined around the change of its steady-state average value random statistical fluctuation
And absolute power.This technology has the advantages that the not normal operating measurement parameter of disturbing reaction heap, and suitable for swimming pool
Reactor, is that measurement absolute power is more convenient, efficiently measuring method.
A kind of reactor nucleus power monitoring system, including：
Two sets of neutron gamma compensated ionization chambers for word noise signal in symmetrical collection reactor；
Micro-current for being amplified to neutron gamma compensated ionization chamber output current signal and be converted to voltage signal is put
Big device；
Signal transacting is carried out to micro current amplifier output signal and DC level signal and neutronic noise signal will be exported
The signal conditioning circuit for being converted to data signal；
Reactor nucleus power is analyzed and processed and realized to micro-current magnification according to signal conditioning circuit output signal
Device, the data analysis of the control of signal conditioning circuit and processing unit.
The signal conditioning circuit includes isolation circuit, DC offset circuit, noise amplifier circuit, the low pass being sequentially connected
Filter circuit, buffer circuit, by isolation circuit, output signal and buffering circuit output signal are converted to the A/D of data signal all the way
Change-over circuit.
The present invention compared with prior art, has the following advantages and advantages：
1st, caused by the inventive method using a large amount of neutrons average current or the statistic fluctuation of voltage as Fundamentals of Measurement,
Measure and obtain under not disturbing reaction heap normally operation, it is adaptable to all reactors, it is not necessary to frequent scale, measurement it is convenient and
Fast, its measurement accuracy is high, the problem of effectively solving big error in existing low-power reactor power measurement and numerous and diverse process.
Brief description of the drawings
Accompanying drawing described herein is used for providing further understanding the embodiment of the present invention, constitutes one of the application
Point, do not constitute the restriction to the embodiment of the present invention.In the accompanying drawings：
Fig. 1 is the structural representation of apparatus of the present invention.
Fig. 2 installs and uses situation map for the present apparatus.
Embodiment
For the object, technical solutions and advantages of the present invention are more clearly understood, with reference to embodiment and accompanying drawing, to this
Invention is described in further detail, and exemplary embodiment and its explanation of the invention is only used for explaining the present invention, does not make
For limitation of the invention.
Embodiment 1
A kind of reactor nucleus power monitoring method, comprises the following steps：
A, after reactor power level is stable, measure reactors using two neutron being arranged symmetrically gamma compensated ionization chambers
In
Sub- noise signal；
B, the FFT to two groups of neutronic noise signal of change time signals, calculate cross-spectral density φXYAnd at normalization
Reason；
C, cross-spectral density is fitted, and calculates a certain specific frequency ω1When cross-spectral density φ 'XY
(ω1)；
D, the parameter obtained according to fitting, obtain reactor fission rate F, so as to obtain reactor absolute power P.
The measuring method be using the average current or the statistic fluctuation of voltage caused by a large amount of neutrons as Fundamentals of Measurement,
Further according to the output signal of reactor Reactor dynamic parameters are determined around the change of its steady-state average value random statistical fluctuation
And absolute power.This technology has the advantages that the not normal operating measurement parameter of disturbing reaction heap, and suitable for swimming pool
Reactor, is that measurement absolute power is more convenient, efficiently measuring method, realizes the survey of the automation to reactor absolute power
Amount.
Power measurement step is specially：
To the FFT of two groups of obtained neutronic noise signal of change time signals, i.e. fast Fourier transform；Then mutual work(is calculated
Rate spectrum density φXY, drafting cross-spectral density curve after the smoothing processing of at least 8 times is carried out to cross-spectral density.
The method of smoothing processing is specially：After current cross-spectral density and last time averaging process are restarted most
The cross-spectral density once calculated afterwards is averaged, and obtains the average cross-spectral density of two groups of noise signals, and is painted
Go out cross-spectral density curve.
According to Koln noise equivalent neutron source it is assumed that the reactor in critical condition, what two ionisation chambers were measured
Reactor noise cross-spectral density is：
Wherein：WX、WYThe detector efficiency of respectively two ionisation chambers；The factor, i.e. driven factor, to U235Make the reactor of fuel, D=0.795；F is exhausted for reactor
To fission rate；The mean charge converted by one neutron of every detection；H (ω) is the transmission function of reactor.
The average current of ionisation chamber output is represented by：
For critical pile, transmission function can approximate representation be：
Wherein：It is in for reactor under delayed criticality state and obtains prompt neutron decay often
Number；β is effective delayed neutron fraction；ω is angular frequency.
Thus convertible export：
Cross-spectral density is normalized, the cross-spectral density φ ' after being normalizedXY：
Wherein：VX、VYRespectively two groups noise signal voltage magnitudes；AX、AYRespectively two groups
Noise signal multiplication factor.
Then cross-spectral density expression formula is transformed to
Parameter fitting model y=f (x, a are set up by above formulai) nonlinear function, reflect ω and φ 'XYDependence close
System, A, ι, β are equivalent to aiFor undetermined parameter.Using Labview Software Development Platform for Virtual Instruments, with non-linear least square
Method fitting tool, i.e., using the least square set that parameter is determined using Levenberg-Marquardt algorithms, the set is defeated
Enter the best fit of data point (x, y), data point can be by nonlinear function y=f (x, ai) represent, wherein aiIt is the set of parameter.
Using Non-linear least-square curve fitting parameter input parameter A, ι, β fitting initial value, the setting of initial value according to
According to reactor core physical theory calculate obtain dynamic parameter value be configured, obtain fitting Reactor dynamic parameters A, ι,
β。
And cross-spectral density is obtained using fitting, calculate a certain specific frequency ω of Frequency1When crosspower spectrum it is close
Spend φ 'XY(ω1), selected ω1λ should be metmax《ω1《αc, λmax=14 be the maximum of six delayed-neutron precursor decay coefficients
Value, i.e., 14《ω1, therefore desirable f1=3, ω1》18.84, αcIt is changing value, and ω1Value it is the smaller the better, typically take 18.84.
The cross-spectral density of neutronic noise signal is after normalized, and reactor fission rate F should be expressed as
The parameter and the cross-spectral density φ ' of calculating obtained by using curve matchingXY(ω1), calculate reactor
Fission rate.
Reactor absolute power P=P0F, wherein, P0Refer to the energy that a nuclear fission is discharged.One single U235Core
About 3.2 × 10 can be sent during fission-11W/s energy.For using U235As the reactor of fuel, according to P=3.2 ×
10-11F can calculate reactor absolute power P.
Embodiment 2
As shown in figure 1, a kind of reactor nucleus power monitoring system based on the above method, including：
Two sets of neutron gamma compensated ionization chambers for word noise signal in symmetrical collection reactor；
Micro-current for being amplified to neutron gamma compensated ionization chamber output current signal and be converted to voltage signal is put
Big device；
Signal transacting is carried out to micro current amplifier output signal and DC level signal and neutronic noise signal will be exported
The signal conditioning circuit for being converted to data signal；
Reactor nucleus power is analyzed and processed and realized to micro-current magnification according to signal conditioning circuit output signal
Device, the data analysis of the control of signal conditioning circuit and processing unit.
Two sets of neutron gamma compensated ionization chambers constitute primary instrument, micro current amplifier, signal conditioning circuit and data analysis
Secondary meter is constituted with processing unit.Specifically, as shown in Fig. 2 being arranged symmetrically 2 between reactor core peripheral board and bracketplant
DL125 type neutron gamma compensated ionization chambers, for gathering pile neutron noise signal.The design and assembly of neutron gamma compensated ionization chamber into
Kit form, ionization chamber enclosure shape is in suspended state, to reduce interference.High voltage power supply is used to be supplied for neutron gamma compensated ionization chamber
Electricity, the excitation type converter type high voltage power supply for employing 2 independent continuously adjustabes provides required positive/negative electricity to two ionisation chambers
Pressure, adjusts converter drive signal amplitude, reaches the purpose of adjustment output high pressure, output voltage：0~± 500V continuously adjustabes；
Low-tension supply is supplied to the necessary dc source of low current normal amplifier operation.
The current signal of 2 neutron gamma compensated ionization chamber outputs is transferred to micro current amplifier by double-shielded cable,
Micro current amplifier is amplified to current signal and is converted to 0~10V voltage signal.Micro current amplifier is provided with different
Multiplication factor gear, data analysis putting according to the current signal size adjust automatically low current amplifier of acquisition with processing unit
Big gear.
Signal conditioning circuit has two-way, each is attached on two neutron gamma compensated ionization chambers, it includes what is be sequentially connected
Isolation circuit, DC offset circuit, noise amplifier circuit, low-pass filter circuit, buffer circuit and A/D change-over circuits.
The two-way DC level signal that signal conditioning circuit receives micro current amplifier output is carried out after isolation processing to it
Direct current signal is transmitted directly to A/D change-over circuits all the way, and another road is passed after DC compensation, programming amplifying and low-pass filtering treatment
Give A/D change-over circuits.It is controlled by data analysis and processing unit for DC offset circuit, noise amplifier circuit, is passed through
16 DA arbitrarily regulations are directly added into direct current biasing component, complete DC compensation, its dc offset range：0~10V, direct current is mended
Repay precision：±1mV.The arbitrary disposition of programming amplifying can also be realized simultaneously, specific multiplication factor has：1、10、50、100、200、
500.The size of signal amplitude adjust automatically DC compensation and the putting of signal of the data analysis with processing unit according to collection feedback
Big multiple.
Data analysis includes processor, operating system and application program with processing unit, completes the analysis and processing of signal.
Its application program is completed based on the method in embodiment 1, and the development platform of software is used as using Labview virtual instrument techniques；Should
Realized with program and low current amplifier gear is configured and read, control its fluid drive, and its output amplitude is carried out
Detection；DC level is compensated automatically；Signal adaptation unit gain and filtering parameter are configured and read；To A/D
Sample frequency and sampling length are configured；Control A/D conversion start and stop；The data cached readings of A/D and display；From power
Spectrum density is analyzed with showing with cross-spectral density；Nonlinear least square method dynamic parameter is fitted；Absolute power is calculated.
Based on the system, it is embodied as process and is：
When reactor starts lifting power, startup power monitoring system, system is by automatic measurement reactor noise.Micro- electricity
Stream amplifier is provided with different multiplication factor gears, as reactor capability constantly rises, is automatically controlled by Labview softwares
Micro current amplifier constantly converts gear, reduces multiplication factor, during opposite power reduction, low current amplifier will increase times magnification
Count, then low current amplifier converts a signal into voltage signal output.
After reactor capability is stable, pile neutron noise signal is nursed one's health and gathered, two compensated neutron γ
Two groups of neutronic noise current signals of compensated ionization chamber's measurement are respectively divided into two-way, are all the way DC level passage, direct measurement is straight
Flow level magnitude；Another road is neutronic noise passage, and noise signal conditioning is carried out to neutronic noise, and signal condition step is as follows：
DC compensation：Level according to neutronic noise passage carries out DC compensation to neutron noise signal, in removal
Flip-flop in sub- noise signal, compensation way uses negative feedback control, and dc offset accuracy is 2mv, i.e., neutronic noise is led to
Road When, DC compensation will be carried out automatically, and v is neutronic noise channel voltage, and A is current noise multiplication factor.
Noise amplifies：Neutron noise signal is amplified step by step after DC compensation, signal condition equipment multiplication factor has：
1、10、50、100、200、500.Neutronic noise signal is precalculated according to A1After amplifying again, judge whether noise signal outranges
(± 5V), does not outrange such as, then it is A to set noise signal multiplication factor1, then A is amplified in precomputation again2Times noise signal is
No to outrange, noise signal will continue to amplify if not outranging, then outranged, and reduction multiplication factor is back to A1Times.
LPF：Corner frequency ω according to the cross-spectral density of reactor is equal to prompt neutron decay constant αcI.e.
The π f=α of ω=2c, then signal analysis frequencyTherefore noise signal selects setting to be more than firstFrequency carries out low pass filtered
Ripple, signal condition equipment LPF gear has：100Hz、200Hz、300Hz、500Hz.
When lifting or decline occurs in reactor power level, then low current amplifier amplification gear changes, now in
Sub- noise channel multiplication factor will be set to 1 times, and after then power level is stable, system will be filtered to noise signal again
The operations such as ripple, DC compensation, noise amplification.
Two-way neutronic noise passage synchronizes collection after signal condition with two-way DC level passage, obtains two groups
The DC level and neutronic noise signal of neutron gamma compensated ionization chamber.
System of the present invention using based on PXI buses standardization and modular technology, improve system reliability and
Servicing ease.Realize the automatic measurement to reactor absolute power and improve measurement accuracy, efficiently solve existing
There is the problems such as error is greatly in low-power reactor power measurement and process is numerous and diverse.
Above-described embodiment, has been carried out further to the purpose of the present invention, technical scheme and beneficial effect
Describe in detail, should be understood that the embodiment that the foregoing is only the present invention, be not intended to limit the present invention
Protection domain, within the spirit and principles of the invention, any modification, equivalent substitution and improvements done etc. all should be included
Within protection scope of the present invention.
Claims (8)
1. a kind of reactor nucleus power monitoring method, it is characterised in that comprise the following steps：
A, after reactor power level is stable, measured using two neutron being arranged symmetrically gamma compensated ionization chambers in reactors
Sub- noise signal；
B, the FFT to two groups of neutronic noise signal of change time signals, calculate cross-spectral density φXYAnd normalized；
C, cross-spectral density is fitted, and calculates frequencies omega1When cross-spectral density φ 'XY(ω1)；
D, the parameter obtained according to fitting, obtain reactor fission rate F, so as to obtain reactor absolute power P.
2. a kind of reactor nucleus power monitoring method according to claim 1, it is characterised in that：In step B, in addition to pair
The smoothing processing of cross-spectral density, the number of times of the smoothing processing is more than or equal to 8 times.
3. a kind of reactor nucleus power monitoring method according to claim 2, it is characterised in that the side of the smoothing processing
Method is specially：The cross-spectral density that current cross-spectral density and last time effective survey calculation are obtained is averaged, and is obtained
The average cross-spectral density of two groups of noise signals is obtained, and draws cross-spectral density curve.
4. a kind of reactor nucleus power monitoring method according to claim 1, it is characterised in that crosspower spectrum after normalization
Density φ 'XYFor：
Wherein, A is the constant related to reactor power level, ionisation chamber detection efficient；β is
Effective delayed neutron fraction；ω is angular frequency；ι is prompt neutron removal lifetime.
5. a kind of reactor nucleus power monitoring method according to claim 4, it is characterised in that step C is using non-linear
Least square method is fitted, and is specially：Fitting using Non-linear least-square curve fitting parameter input parameter A, ι, β is initial
Value, the installation warrants reactor core physical theory of initial value calculates the dynamic parameter value obtained and is configured, and obtains fitting
Reactor dynamic parameters A, ι, β.
6. a kind of reactor nucleus power monitoring method according to claim 1, it is characterised in that in the step D, reaction
Heap fission rate F is：
Wherein, D refers to driven factor, and β is effective delayed neutron fraction；
Reactor absolute power P is：P=P0F, wherein, P0Refer to the energy that a nuclear fission is discharged.
7. a kind of reactor nucleus power monitoring system, it is characterised in that including：
Two sets of neutron gamma compensated ionization chambers for word noise signal in symmetrical collection reactor；
For being amplified to neutron gamma compensated ionization chamber output current signal and being converted to the micro current amplifier of voltage signal；
Signal transacting is carried out to micro current amplifier output signal and turns output DC level signal and neutronic noise signal
It is changed to the signal conditioning circuit of data signal；
Reactor nucleus power is analyzed and processed according to signal conditioning circuit output signal and realized to micro current amplifier, letter
The data analysis of the control of number modulate circuit and processing unit.
8. a kind of reactor nucleus power monitoring system according to claim 1, it is characterised in that the signal conditioning circuit
Including the isolation circuit being sequentially connected, DC offset circuit, noise amplifier circuit, low-pass filter circuit, buffer circuit, will isolation
Output signal and buffering circuit output signal are converted to the A/D change-over circuits of data signal to circuit all the way.
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| CN115295179A (en) * | 2022-08-22 | 2022-11-04 | 中国原子能科学研究院 | Compensation method for reactor power measurement |
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