CN109215823A - A kind of measurement method and system of nuclear reactor three-dimensional multigroup power spectrum - Google Patents
A kind of measurement method and system of nuclear reactor three-dimensional multigroup power spectrum Download PDFInfo
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Abstract
The present invention provides the measurement method and system of a kind of nuclear reactor three-dimensional multigroup power spectrum, and the method includes arranging at least one neutron detector at random in nuclear reactor；Theoretically calculate the response distribution of the multiple types neutron detector of the three-dimensional spectral distribution of nuclear reactor, the reading of multiple types neutron detector and hypothesis；Calculate the true survey measurements of each type neutron detector and the ratio of theoretical reading；Nuclear reactor any position is derived into the ratio diffusion of the true survey measurements of each type neutron detector and theoretical reading；The reconstruct response of each type neutron detector under calculation assumption detector length；According to selected neutron detector and energy group, the three-dimensional power spectrum of any position is solved.The present invention is stablized by theoretically neutron detector reading with true survey measurements ratio, and theoretical calculation solves three-dimensional spectral distribution in conjunction with above-mentioned ratio, solves the problems, such as that the prior art lacks effective means for the reactor measurement of power spectrum height change.
Description
Technical field
The present invention relates to the measurement method of nuclear technology field more particularly to a kind of nuclear reactor three-dimensional multigroup power spectrum and it is
System.
Background technique
Nuclear reactor, which refers to react using nuclear fission, generates amount of heat, and is passed using all kinds of working medium to the heat
It leads, and realizes the device that effective radioactivity contains and pile reactivity effectively controls.Therefore having in real time to nuclear reactor
Effect monitoring is the key that realize that the radioactivity of reactor contains and reactor is effectively cooling.Because in the three-dimensional space of heap in-core
The neutron distribution in different-energy section will lead to the difference of heap in-core three-dimensional power distribution, and then influence heap in-core difference area
The cooling effect in domain is different, cooling insufficient so as to cause regional area fever too many, to exacerbate fuel and involucrum
Failure probability in accident, causes radioactivity to leak, and effective monitoring to three-dimensional spectral distribution is also experimental reactor or grinds
Study carefully the prerequisite that in-pile irradiation duct carries out material or irradiation experiment.
In order to effectively monitor reactor Neutron flux distribution real time information, usually in reactor core inner or
Person's disposed outside detector, the arrangement of different reactors have different characteristics.
In the In-core Instrumentation of traditional pressurized water reactor, generally use in heap in packaged type or heap internally-fixed
Sub- detector carries out the measurement of detector readings.Main current indication is proportional to the absorption reaction rate of detector active material
Or fission reaction rate.The U235 miniature fission chamber of high degree of enrichment is used with the packaged type detector of pressurized water reactor PWR.
Such as 50 probe access are arranged in 157 components of presurized water reactor.By the way that detector probe is repeatedly put into heap in-core, shape
At three-dimensional reactor core detector readings, (packaged type detector measures current indication while mobile in each channel, leads to
It crosses and simplifies merger, the three dimension detector reading distribution of 50*57 can be obtained.
With the stationary detector of PWR, then in the position close to 50 Measurement channels, axial arrangement is uniformly or uneven
Segmented detector, to obtain detector readings.It is assumed that 42 probe access of radial arrangement, and axially arrange 5 sections
(or 7 sections etc.) SPND sensitive segment.The three dimension detector reading distribution of 42*5 can then be obtained.
The measurement point of current pressurized water reactor is always limited, usually in pressurized water reactor, the survey of spectral distribution
Amount is carried out simultaneously with power distribution measuring.After being combined by theoretical value with measured value, processing obtains three-dimensional power point
When cloth, a hypothesis has been done: the ratio P of theoretical power (horse-power) distribution and measurement power distribution i.e. in pressurized water reactormes/PprdWith
Theoretical fast group/hot group energy Spectral structure and the fast group of measurement and hot group energy Spectral structure φ1 mes/φ1 prdOr φ2 mes/φ2 prdIt is phase
Together.Because power distribution is substantially the co-determination by fast group and hot group energy Spectral structure, the potential meaning of above-mentioned hypothesis
Are as follows: it is assumed that the ratio of the fast group of theoretical calculation and hot group fluxWith the fast group energy spectrum of measurement and the ratio of hot group energy spectrum
ValueIt is identical.
Since for pressurized water reactor, the φ of calculating1/φ2Accuracy, be difficult to obtain by existing technological means
?.Because cannot achieve φ when scene only has a kind of detector1/φ2Calculating.
However, this hypothesis theoretical calculationBe accurately, for presurized water reactor may relatively rationally.But
For the reactor changed with height power spectrum, then it may cause large error, therefore the prior art changes height power spectrum
Reactor measurement lack effective means.
Summary of the invention
In order to solve the above technical problems, the present invention provides a kind of measurement method of nuclear reactor three-dimensional multigroup power spectrum and is
System.
A kind of measurement method of nuclear reactor three-dimensional multigroup power spectrum provided by the invention, which comprises
Step S401, at least one neutron detector is arranged at random in nuclear reactor；
Step S402, the three-dimensional spectral distribution of nuclear reactor, the reading of multiple types neutron detector are theoretically calculated
And the response distribution of the multiple types neutron detector assumed；
Step S403, the true survey measurements of each type neutron detector and the ratio theoretically read are calculated；
Step S404, the true survey measurements of each type neutron detector is pushed away with the ratio diffusion theoretically read
Spread out to any position nuclear reactor Quan Dui；
Step S405, the reconstruct of each type neutron detector responds under calculation assumption detector length；
Step S406, the reconstruct response for calculating each type neutron detector of reconstruct is true with corresponding neutron detector
The standard deviation of actual measured amount reading；
Step S407, according to the standard deviation of each type neutron detector, the row of multiple types neutron detector is carried out
Name；
Step S408, compare the quantity of neutron detector and the quantity of group, select neutron detector and energy group；
Step S409, according to selected neutron detector and energy group, the three-dimensional power spectrum of any position is solved.
Further, the step S402 specifically:
The step of theoretically calculating the three-dimensional spectral distribution of nuclear reactor according to following formula specially φprd(x,y,
Z, g), g=1, N, wherein g is energy group, is divided into N number of group, φprd(x, y, z, g) is theoretic three-dimensional power spectrum；
The reading of multiple types neutron detector: RR is theoretically calculated according to following formulaprd(X, Y, Z, i), i=1,
M, wherein X, Y, Z are the actual position at the place of i-th kind of detector, and M is the type of detector；
According to following formula theoretically the multiple types neutron detector of calculation assumption response distribution: RRXprd(x,
Y, z, i), i=1, M, using different types of neutron detector pre-set dimension L (i), i=1, M；
The response distribution that physical significance has the multiple types neutron detector of hypothesis is obtained according to following formula:
Further, the method also includes:
According to the three-dimensional power spectrum of solution, the three-dimensional power spectrum is input to the multiple types neutron detector of step S402
Response distribution formulaIn φprd(x,y,
Z, g), iterate to calculate the three-dimensional power spectrum convergence until each energy group of nuclear reactor any position.
Further, the three-dimensional power spectrum is input to step S402 theoretically by the three-dimensional power spectrum according to solution
Multiple types neutron detector response distribution formula
In φprd(x, y, z, g), iteration meter
Calculate the three-dimensional power spectrum convergence until each of nuclear reactor any position energy group specifically:
According to the three-dimensional power spectrum of solution, the three-dimensional power spectrum is input in step S402 in theoretic multiple types
The response distribution formula of sub- detectorIn
φprd(x, y, z, g) repeats step S403 to S409, until the three-dimensional power spectrum of each energy group meets:
The n is the number of iterations, and the σ is
Convergence criterion, the φmesThe three-dimensional power spectrum that (x, y, z, j) is j-th group.
Further, the true survey measurements for calculating each type neutron detector and the ratio theoretically read
Method is to be realized using following formula:
The RRprd(X, Y, Z, i) is the theory of neutron detector
Upper reading, the RRmes(X, Y, Z, i) is the true survey measurements of neutron detector, and the DIV (X, Y, Z, i) is every type
The true survey measurements of type neutron detector and the ratio theoretically read.
Further, the step S405 is specifically included using every type under following formula calculation assumption detector length
The reconstruct of type neutron detector responds:
RRXrec(x, y, z, i)=RRXprd(x, y, z, i) × DIV ' (x, y, z, i), the RRXrec(x, y, z, i) is every
The reconstruct of seed type neutron detector responds, RRprdThe theoretically reading of (X, Y, Z, i) each type neutron detector, DIV '
(x, y, z, i) is that nuclear reaction is derived in the true survey measurements of each type neutron detector and the ratio theoretically read diffusion
Any position heap Quan Dui as a result, the i be detector type.
Further, the step S406, which is specifically included, obtains the calibration difference using following formula:
σ (i)=RRmes(X,Y,Z,i)-RRrec(X, Y, Z, i), RRmes(X, Y, Z, i) is the true survey of neutron detector
Amount reading, RRrec(X, Y, Z, i) is the reconstruct response of corresponding neutron detector, and the σ (i) is standard deviation.
Further, the S408 is specifically included:
When neutron type photodetector quantity M is more than or equal to group's quantity N, picked out in N kind from M kind neutron detector
Sub- detector, by N number of group as N number of energy group, the standard deviation of the N kind neutron detector comes the preceding N of M kind neutron detector
Position；
When neutron type photodetector quantity M is less than group's quantity N, all M kind neutron detectors are selected, by N number of group of simplification
Merger is (N-M) a energy group.
Further, the step S409 is specifically included:
It is assumed that the length of A seed type neutron detector and default neutron detector, establishes A equation:
The x, y, z are core
Reactor core any position；
The ratio that suppose there is the three-dimensional power spectrum of B kind energy group, establishes B equation:
φmes(x, y, z, j)=fj,k×φmes(x, y, z, k), the φmesThe three-dimensional energy that (x, y, z, j) is j-th group
Spectrum, φmesThe three-dimensional power spectrum that (x, y, z, k) is k-th group, fj,kFor the ratio between above-mentioned two energy group；
When judging A+B >=N, the N is group's quantity, according to the A equation and the B equation, utilizes minimum two
Multiply principle, calculates three-dimensional multigroup power spectrum φmes(x,y,z,k)。
A kind of measuring system of nuclear reactor three-dimensional multigroup power spectrum provided by the invention, the system comprises:
Setting unit, for arranging at least one neutron detector at random in nuclear reactor；
First computing unit, for theoretically calculating three-dimensional spectral distribution, the multiple types neutron detection of nuclear reactor
The response of the multiple types neutron detector of the reading and hypothesis of device is distributed；
Second computing unit, for calculating the true survey measurements of each type neutron detector and theoretically reading
Ratio；
Unit is derived, for expanding the true survey measurements of each type neutron detector with the ratio theoretically read
It dissipates and derives any position nuclear reactor Quan Dui；
Third computing unit, the reconstruct response for each type neutron detector under calculation assumption detector length；
4th computing unit responds and corresponding neutron for calculating the reconstruct of each type neutron detector of reconstruct
The standard deviation of the true survey measurements of detector；
Sequencing unit carries out multiple types neutron detector for the standard deviation according to each type neutron detector
Ranking；
Comparing unit selectes neutron detector and energy group for comparing the quantity of neutron detector and the quantity of group；
5th computing unit, for solving the three-dimensional power spectrum of any position according to selected neutron detector and energy group.
The invention has the following beneficial effects:
The present invention passes through the detection and theoretic calculating of neutron detector, obtains theoretic three-dimensional gamma-spectrometric data
With the three-dimensional gamma-spectrometric data of detection, full heap is derived by the method for mathematics and calculates the three-dimensional of entire reactor any position
Multigroup power spectrum solves the problems, such as to lack effective means for the reactor measurement of height power spectrum variation caused by the prior art.
Detailed description of the invention
In order to more clearly explain the embodiment of the invention or the technical proposal in the existing technology, below will to embodiment or
Attached drawing needed to be used in the description of the prior art is briefly described, it should be apparent that, the accompanying drawings in the following description is only
Some embodiments of the present invention, for those of ordinary skill in the art, without creative efforts, also
Other drawings may be obtained according to these drawings without any creative labor.
Fig. 1 is correct nuclear reactor detector arrangement figure provided in an embodiment of the present invention.
Fig. 2 is the nuclear reactor detector arrangement figure of mistake provided in an embodiment of the present invention.
Fig. 3 is that schematic diagram is derived in the reactivity distribution of O-shaped detector provided in an embodiment of the present invention.
Fig. 4 is the measuring method flow chart of nuclear reactor three-dimensional multigroup power spectrum provided in an embodiment of the present invention.
Fig. 5 is the measuring system structure chart of nuclear reactor three-dimensional multigroup power spectrum provided in an embodiment of the present invention.
Specific embodiment
This patent core content is to obtain three-dimensional gamma-spectrometric data by detection and theoretical calculation, and carry out mathematics and derive
To entire nuclear reactor, and the three-dimensional power spectrum of any position is calculated, to this method and is below in conjunction with drawings and examples
System specific embodiment is described further.
The measurement method and system of a kind of nuclear reactor three-dimensional multigroup power spectrum provided by the invention is described more fully below
Embodiment.
As shown in Figure 1, the embodiment of the invention provides correct nuclear reactor detector arrangement modes, it is assumed that reactor
In arrange M kind detector, the type of every kind of detector is different.Arranging four kinds of (M=4) type of sensors with heap in-core is
Example, X represent X-type detector arrangement, and Y represents Y type detector arrangement, and Z represents Z-type detector arrangement, and O represents O-shaped detector cloth
It sets, a correct detector arrangement form is as shown in Figure 1.For the detector of a certain type, in the arrangement of heap in-core
It should be distributed to full heap as far as possible, the state of full heap can be represented.It should be noted that before realizing that of the invention one is important
It mentions and is that the arrangement of different detectors should cover full heap as far as possible, to guarantee that the arrangement of different detectors covers full heap, therefore it is every
A kind of detector random distribution all in heap.
As shown in Fig. 2, the embodiment of the invention provides the nuclear reactor detector arrangement mode of mistake, it is identical with Fig. 1
Place or four seed type detectors, various types of detector arrangement Relatively centralizeds, be arranged in a certain quadrant of reactor or
In person region, each detector random distribution all in heap is not accomplished.
As shown in figure 3, the reactivity distribution of O-shaped detector provided in an embodiment of the present invention is derived, true detector is utilized
Measured value and theoretical value, carry out the distribution of detector reactivity reconstruct, obtain reactor core any position default detector weight
Structure reactivity value；Other kinds of detector is not considered, only considers O-shaped detector, and reconstruct obtains the default of reactor core any position
Detector reactivity.
As shown in figure 4, the measurement method of nuclear reactor three-dimensional multigroup power spectrum provided in an embodiment of the present invention, the method
Include:
Step S401, at least one neutron detector is arranged at random in nuclear reaction.
In the present embodiment, it in order to solve the problems, such as the measurement of multigroup power spectrum, needs to arrange that multiple types are visited in reactor
Survey device.The neutron detector of heap in-core mainly provides the information in relation to the spatial distribution of neutron flux rate distribution in reactor core,
Cube is small, and the service life is long, does not influence the distribution of the neutron field of reactor core.It is general to be detected using self-sufficiency other than small-sized fission chamber
Device.Typical self-powered detector includes: the emissive materials such as rhodium (Rh), vanadium (V), cobalt (Co), europium (Eu).In addition in some
Sub- detector such as scandium, cadmium etc. is also applied to the detection of neutron.Other γ type neutron detectors are also: using lead, magnesium, Inco nickel 600
Equal materials make the self-powered gamma detector etc. of emitter.
The embodiment of the present invention is not limited to using which kind of neutron detector, because the essence or principle of neutron detector, are all
The a series of object of neutron flux locating for sensitive material and detector by neutron detector (or neutron fluence rate)
Reason reaction, to obtain the electric current of measurement detector.I.e. the current indication of detector reacts total with all kinds of of neutron detector
Reactivity is that direct proportion is relevant.Typical such as (n, β) reactivity or (n, γ) reactivity etc..(n, γ) is reacted, is generated
γ may further occurrence Compton scattering, photoelectric effect obtains the electric current of detector.
Step S402, the three-dimensional spectral distribution of nuclear reactor, the reading of multiple types neutron detector are theoretically calculated
And the response distribution of the multiple types neutron detector assumed.
According to the reactor core state of actual motion nuclear reactor, the reactor theory calculated result of best estimate is constructed.The reason
It is set according to true nuclear reactor power history, stick position, critical condition or temperature, pressure condition etc. using core by calculated result
It counts software and theoretical calculation is carried out to nuclear reactor.These theoretical calculations itself are a kind of estimations to true nuclear reactor, but away from
It is strictly with a distance from some from true nuclear reactor.Obviously reactor core is being operated normally without under any abnormal conditions, nuclear design software
The calculated results and the difference of actual response heap be very little.This also demonstrates the reliability and drawing of design software
The nuclear reactor of upper design and true reactor difference are little, demonstrate according to the nuclear reactor safety carried out on drawing point
The reliability etc. of analysis.However, true nuclear reactor is such as surveyed there is always likely to be the influence of some potential abnormal factors
Amount uncertainty or manufacturing process error etc., all may cause true nuclear reactor and theoretical calculation nuclear reactor exists
Difference.And the value of on-line monitoring system itself, in that the deviation is visited in reasonable utilization detector resource, realization
It surveys and corrects, to obtain true nuclear reactor state.
The three-dimensional spectral distribution of nuclear reactor: φ is theoretically calculated according to following formulaprd(x, y, z, g), g=1, N,
Wherein g is energy group, is divided into N number of group, x, y, and z is nuclear reactor any position, φprd(x, y, z, g) is theoretic three-dimensional energy
Spectrum.It is 6~20 that typical fast reactor, which calculates energy group's number, and calculating energy group's number of typical pressurized water reactor is 2~6；
The reading of multiple types neutron detector: RR is theoretically calculated according to following formulaprd(X, Y, Z, i), i=1,
M, wherein X, Y, Z are the actual position at the place of i-th kind of detector, and i is the type of neutron detector, and M is the type of detector
Quantity.It should be strongly noted that RRprdTheory reading distribution is the detector readings under true detector size,
Detector length may be longer, such as the detector sensitive segment of typical Rh detector is 20~30cm etc.；
According to following formula theoretically the multiple types neutron detector of calculation assumption response distribution: RRXprd(x,
Y, z, i), i=1, M, using different types of neutron detector pre-set dimension L (i), i=1, M, length may be shorter at this time.
The selection of neutron detector preset length predominantly meets the required precision of nuclear reactor three-dimensional power spectrum calculating.Typically
Preset length are as follows: every slice width degree when carrying out axis layering (20~30 layers axial) to reactor core active region height, about 2~
10cm.Typically neutron detector preset length is smaller than the detector length of actual response heap arrangement.In default length
In the case of degree, it is further assumed that neutron detector can be placed into reactor core any position x, y, z, its default neutron is calculated at this time and is visited
Survey the response of device；
According to following formula theoretically the multiple types neutron detector of calculation assumption macroscopic cross section distribution ∑ (x,
Y, z, i, g), i=1, M；G=1, M, neutron detector length is L (i), i=1, M at this time.Obviously, it is obtained according to following formula
Physical significance has the response of the multiple types neutron detector of hypothesis to be distributed are as follows:
It should be noted that call typical Nuclear design software (as commercial fast reactor nuclear design software ERANOS,
The water-water reactor software of independent research fast reactor soft SA RAX or the presurized water reactor nuclear design software SCIENCE of commercialization, independent research
COCO above-mentioned parameter can) be calculated.
Step S403, the true survey measurements of each type neutron detector and the ratio theoretically read are calculated.
It should be noted that this step need to the true survey measurements of each type neutron detector with theoretically read
Several ratios are calculated；Here by taking i-th kind of neutron detector as an example, by taking O-shaped neutron detector shown in Fig. 3 as an example.
Calculate the true survey measurements of O-shaped detector and the formula of the ratio theoretically read specifically:
The RRprd(X, Y, Z, i) is the theory of neutron detector
Upper reading, the RRmes(X, Y, Z, i) is the true survey measurements of neutron detector, it should be noted that the present embodiment provides
The equally applicable formula of other kinds of neutron detector.
Step S404, the true survey measurements of each type neutron detector is pushed away with the ratio diffusion theoretically read
Spread out to any position nuclear reactor Quan Dui.
DIV ' (x, y, z, i)=f (DIV (X, Y, Z, i) → x, y, z), x, y, z are any position Quan Dui；Typical diffusion
It is many to derive algorithm, there is Exchanger Efficiency with Weight Coefficient Method, three-dimensional planar thin plate spline fitting process, the direct method of development of multinomial etc., f
(DIV (X, Y, Z, i) → x, y, z) is straight using above-mentioned Exchanger Efficiency with Weight Coefficient Method, three three-dimensional planar thin plate spline fitting process and multinomial
Connect the function of the methods of method of development.
Step S405, the reconstruct of each type neutron detector responds under calculation assumption detector length.
The step is specially the reconstruct using each type neutron detector under following formula calculation assumption detector length
Response: RRXrec(x, y, z, i)=RRXprd(x, y, z, i) × DIV ' (x, y, z, i), RRXrec(x, y, z, i) is neutron detection
The reconstruct of device responds.
Step S406, the reconstruct response for calculating each type neutron detector of reconstruct is true with corresponding neutron detector
The standard deviation of actual measured amount reading.
For the O-shaped neutron detector shown in Fig. 3, O-shaped neutron detector uncertainty quantization is carried out；Standard deviation uses
Following formula obtain: σ (i)=RRmes(X,Y,Z,i)-RRrec(X, Y, Z, i), RRmes(X, Y, Z, i) is O-shaped neutron detector
True survey measurements, RRrec(X, Y, Z, i) is the reconstruct response of O-shaped neutron detector；Other kinds of neutron detector is used
Same method calculates standard deviation.
Optionally, the deviation average of each type neutron detector can also be calculated.
It should be noted that still taking what is shown in fig. 3 as an example, calculating O-shaped neutron detector reconstruct response and being read with true measurement
Number deviation:
Calculate the deviation average of all O-shaped neutron detectorsCalculation method is by all O-shaped neutron detections
For device deviation adduction then divided by O-shaped neutron detector quantity, the deviation that can similarly calculate other types neutron detector is average
Value.
Step S407, according to the standard deviation of each type neutron detector, the row of multiple types neutron detector is carried out
Name.
It is ranked up for the reconstruct uncertainty of different types of neutron detector, filters out the detection of most worthy
Device type, i.e. σ (i) > σ (j)；Namely the standard deviation the big more can come front.
Step S408, compare the quantity of neutron detector type and the quantity of group, select neutron detector and energy group.
It should be noted that complete the sequence of M seed type neutron detector in step S 407, for there is N number of group
Situation picks out N kind neutron detector as M >=N from M kind neutron detector, by N number of group as it is N number of can group into
The solution of the three-dimensional power spectrum of the N number of energy group of row.
It should be noted that when selecting N kind neutron detector, it is big to need to select top n standard deviation；N group is all
It is selected.
As M < N, when the lazy weight of neutron detector type is to meet high accuracy three-dimensional power spectrum reconfiguration requirement, need
Group in nuclear reactor is simplified and merger, typical method include:
The φprd(i) the three-dimensional power spectrum for being theoretically i-th group, the φprd
It (k) is the three-dimensional power spectrum of theoretically kth group；The φmes(i) the three-dimensional power spectrum for being true i-th group, the φmes(k) it is
The three-dimensional power spectrum of true kth group.
In order to calculate N number of group of three-dimensional power spectrum, because the quantity of group is greater than the quantity of neutron detector type, choose
All M kind neutron detectors are selected, in addition to needing to be calculated according to neutron detector type, it is also necessary to N number of group is simplified and
Merger is (N-M) a energy group, and a energy group's ratio of supplement calculation (N-M) needs to constitute altogether (N-M) a energy group, and calculates (N-M)
It is a can between group it is three-dimensional can Spectrum ratio, it is each can group three-dimensional power spectrum calculation method referring to theoretically being calculated in step S402
The step of three-dimensional spectral distribution of nuclear reactor.
Step S409, according to selected neutron detector and energy group, the three-dimensional power spectrum of any position is solved.
It should be noted that being calculated according to ratio between the response distribution and group of the multiple types neutron detector of hypothesis
Three-dimensional multigroup power spectrum.
It is assumed that the length of A seed type neutron detector and default neutron detector, is obtained by step S402 and assumes A kind
A equation is established in the response distribution of type neutron detector:
The x, y, z are core
Reactor core any position；
The ratio that suppose there is the three-dimensional power spectrum of B kind energy group constructs B equation using step S409:
φmes(x, y, z, j)=fj,k×φmes(x, y, z, k), the φmesThe three-dimensional energy that (x, y, z, j) is j-th group
Spectrum, φmesThe three-dimensional power spectrum that (x, y, z, k) is k-th group, fj,kFor the ratio between above-mentioned two energy group.
When judging A+B >=N, the N is group's quantity, according to the A equation and the B equation, utilizes minimum two
Multiply principle, any position x, the three-dimensional power spectrum of y, z, also referred to as three-dimensional multigroup power spectrum φ can be obtainedmes(x,y,z,k)。
Further, according to the three-dimensional power spectrum of solution, three-dimensional power spectrum is input to the theoretic multiple types of step S402
The response distribution formula of type neutron detectorIn
Theoretic φprd(x, y, z, g) iterates to calculate the three-dimensional power spectrum until nuclear reactor any position x, y, each of z energy group
Convergence.
In order to obtain the higher three-dimensional power spectrum of precision, step S409 is obtained into the reason that three-dimensional power spectrum is input to step S402
In response distribution formula by the multiple types neutron detector of upper hypothesis, three-dimensional power spectrum substitution is obtained theoretically with calculating
φprd(x, y, z, g) repeats S403 to S409, until the three-dimensional power spectrum of each energy group meets:
The n is the number of iterations, and the σ is
Convergence criterion, the φmesThe three-dimensional power spectrum that (x, y, z, j) is j-th group.
As shown in figure 5, the measuring system of nuclear reactor three-dimensional multigroup power spectrum provided in an embodiment of the present invention, the system
Include:
Setting unit 51, for arranging at least one neutron detector at random in nuclear reactor；
First computing unit 52, for theoretically calculating the three-dimensional spectral distribution of nuclear reactor, multiple types neutron is visited
Survey the response distribution of the reading of device and the multiple types neutron detector of hypothesis；
Second computing unit 53, for calculating the true survey measurements of each type neutron detector and theoretically reading
Ratio；
Unit 54 is derived, for by the true survey measurements of each type neutron detector and the ratio that theoretically reads
Any position nuclear reactor Quan Dui is derived in diffusion；
Third computing unit 55, the reconstruct response for each type neutron detector under calculation assumption detector length；
4th computing unit 56, for calculate reconstruct each type neutron detector reconstruct response with it is corresponding in
The standard deviation of the sub- true survey measurements of detector；
Sequencing unit 57 carries out multiple types neutron detector for the standard deviation according to each type neutron detector
Ranking；
Comparing unit 58 selectes neutron detector and energy group for comparing the quantity of neutron detector and the quantity of group；
5th computing unit 59, for solving the three-dimensional energy of any position according to selected neutron detector and energy group
Spectrum.
The invention has the following beneficial effects:
The present invention passes through the detection and theoretic calculating of neutron detector, obtains theoretic three-dimensional gamma-spectrometric data
With the three-dimensional gamma-spectrometric data of detection, full heap is derived by the method for mathematics and calculates the three-dimensional of entire reactor any position
Multigroup power spectrum solves the problems, such as to lack effective means for the reactor measurement of height power spectrum variation caused by the prior art.
Those of ordinary skill is understood that realize all or part of the process in above-described embodiment method, is that can pass through
Computer program is completed to instruct relevant hardware, and the program can be stored in a computer-readable storage medium,
The program is when being executed, it may include such as the process of the embodiment of above-mentioned each method.Wherein, the storage medium can for magnetic disk,
CD, read-only memory (Read-Only Memory, ROM) or random access memory (Random Access
Memory, RAM) etc..
The above content is a further detailed description of the present invention in conjunction with specific preferred embodiments, cannot recognize
Fixed specific implementation of the invention is only limited to these instructions.For those of ordinary skill in the art to which the present invention belongs,
Without departing from the inventive concept of the premise, a number of simple deductions or replacements can also be made, all shall be regarded as belonging to the present invention
Protection scope.
Claims (10)
1. a kind of measurement method of nuclear reactor three-dimensional multigroup power spectrum, which is characterized in that the described method includes:
Step S401, at least one neutron detector is arranged at random in nuclear reactor；
Step S402, theoretically calculate the three-dimensional spectral distribution of nuclear reactor, multiple types neutron detector reading and
It is assumed that multiple types neutron detector response distribution；
Step S403, the true survey measurements of each type neutron detector and the ratio theoretically read are calculated；
Step S404, the true survey measurements of each type neutron detector is derived into core with the ratio diffusion theoretically read
Any position reactor Quan Dui；
Step S405, the reconstruct of each type neutron detector responds under calculation assumption detector length；
Step S406, the reconstruct response for calculating each type neutron detector of reconstruct is really measured with corresponding neutron detector
The standard deviation of reading；
Step S407, according to the standard deviation of each type neutron detector, the ranking of multiple types neutron detector is carried out；
Step S408, compare the quantity of neutron detector and the quantity of group, select neutron detector and energy group；
Step S409, according to selected neutron detector and energy group, the three-dimensional power spectrum of any position is solved.
2. the method as described in claim 1, which is characterized in that the step S402 specifically:
The three-dimensional spectral distribution of nuclear reactor: φ is theoretically calculated according to following formulaprd(x, y, z, g), g=1, N, wherein
G is energy group, is divided into N number of group, x, y, and z is nuclear reactor any position, φprd(x, y, z, g) is theoretic three-dimensional power spectrum；
The reading of multiple types neutron detector: RR is theoretically calculated according to following formulaprd(X, Y, Z, i), i=1, M,
In, X, Y, Z are the actual position at the place of i-th kind of detector, and M is the type of detector；
According to following formula theoretically the multiple types neutron detector of calculation assumption response distribution: RRXprd(x,y,z,
I), i=1, M, using different types of neutron detector pre-set dimension L (i), i=1, M；
The response distribution that physical significance has the multiple types neutron detector of hypothesis is obtained according to following formula:
3. method according to claim 2, which is characterized in that the method also includes:
According to the three-dimensional power spectrum of solution, the three-dimensional power spectrum is input to the response of the multiple types neutron detector of step S402
Distribution formulaIn φprd(x, y, z, g), repeatedly
In generation, calculates the three-dimensional power spectrum convergence until each energy group of nuclear reactor any position.
4. method as claimed in claim 3, which is characterized in that the three-dimensional power spectrum according to solution, by the three-dimensional power spectrum
It is input to the response distribution formula of the theoretic multiple types neutron detector of step S402
In φprd(x, y, z, g), iteration meter
Calculate the three-dimensional power spectrum convergence until each of nuclear reactor any position energy group specifically:
According to the three-dimensional power spectrum of solution, the three-dimensional power spectrum is input to theoretic multiple types neutron detection in step S402
The response distribution formula of deviceIn φprd(x,y,
Z, g), step S403 to S409 is repeated, until the three-dimensional power spectrum of each energy group meets:
The n is the number of iterations, and the σ is that convergence is quasi-
Then, the φmesThe three-dimensional power spectrum that (x, y, z, j) is j-th group.
5. the method as described in claim 1, which is characterized in that the true measurement for calculating each type neutron detector is read
Number is specially to be realized using following formula with the ratio approach theoretically read:
The RRprd(X, Y, Z, i) is the theoretically reading of neutron detector
Number, the RRmes(X, Y, Z, i) is the true survey measurements of neutron detector, and the DIV (X, Y, Z, i) is each type neutron
The true survey measurements of detector and the ratio theoretically read.
6. method as claimed in claim 5, which is characterized in that the step S405, which is specifically included, calculates vacation using following formula
Determine the reconstruct response of each type neutron detector under detector length:
RRXrec(x, y, z, i)=RRXprd(x, y, z, i) × DIV ' (x, y, z, i), the RRXrec(x, y, z, i) is every type
The reconstruct of type neutron detector responds, RRprdThe theoretically reading of (X, Y, Z, i) each type neutron detector, DIV ' (x, y,
Z, i) it is that the full heap of nuclear reactor is derived in the true survey measurements of each type neutron detector and the ratio theoretically read diffusion
Any position as a result, the i be detector type.
7. method as claimed in claim 6, which is characterized in that the step S406, which is specifically included, obtains institute using following formula
State calibration difference:
σ (i)=RRmes(X,Y,Z,i)-RRrec(X, Y, Z, i), RRmes(X, Y, Z, i) is that the true measurement of neutron detector is read
Number, RRrec(X, Y, Z, i) is the reconstruct response of corresponding neutron detector, and the σ (i) is standard deviation.
8. the method for claim 7, which is characterized in that the S408 is specifically included:
When neutron type photodetector quantity M is more than or equal to group's quantity N, N kind neutron detection is picked out from M kind neutron detector
Device, by N number of group as N number of energy group, the standard deviation of the N kind neutron detector comes the top N of M kind neutron detector；
When neutron type photodetector quantity M is less than group's quantity N, all M kind neutron detectors are selected, by N number of group of simplified merger
For (N-M) a energy group.
9. method according to claim 8, which is characterized in that the step S409 is specifically included:
It is assumed that the length of A seed type neutron detector and default neutron detector, establishes A equation:
The x, y, z are nuclear reaction
Heap reactor core any position；
The ratio that suppose there is the three-dimensional power spectrum of B kind energy group, establishes B equation:
φmes(x, y, z, j)=fj,k×φmes(x, y, z, k), the φmesThe three-dimensional power spectrum that (x, y, z, j) is j-th group,
φmesThe three-dimensional power spectrum that (x, y, z, k) is k-th group, fj,kFor the ratio between above-mentioned two energy group；
When judging A+B >=N, the N is group's quantity, according to the A equation and the B equation, utilizes least square original
Reason calculates three-dimensional multigroup power spectrum φmes(x,y,z,k)。
10. a kind of measuring system of nuclear reactor three-dimensional multigroup power spectrum, which is characterized in that the system comprises:
Setting unit, for arranging at least one neutron detector at random in nuclear reactor；
First computing unit, for theoretically calculating the three-dimensional spectral distribution of nuclear reactor, multiple types neutron detector
The response distribution of reading and the multiple types neutron detector assumed；
Second computing unit, for calculating the true survey measurements of each type neutron detector and the ratio theoretically read；
Unit is derived, for deriving the true survey measurements of each type neutron detector with the ratio diffusion theoretically read
To any position nuclear reactor Quan Dui；
Third computing unit, the reconstruct response for each type neutron detector under calculation assumption detector length；
4th computing unit responds and corresponding neutron detector for calculating the reconstruct of each type neutron detector of reconstruct
The standard deviation of true survey measurements；
Sequencing unit carries out the ranking of multiple types neutron detector for the standard deviation according to each type neutron detector；
Comparing unit selectes neutron detector and energy group for comparing the quantity of neutron detector and the quantity of group；
5th computing unit, for solving the three-dimensional power spectrum of any position according to selected neutron detector and energy group.
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