CN107292762A - The recombination radiation source strength backstepping method and system of nuclear power plant's point source line source body source combination - Google Patents
The recombination radiation source strength backstepping method and system of nuclear power plant's point source line source body source combination Download PDFInfo
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Abstract
The invention discloses a kind of recombination radiation source strength backstepping method of nuclear power plant's point source line source body source combination and the recombination radiation source system of point source line source body source combination, in this method, the close rate of multiple positions is obtained by detector, normalization radiation source intensity is spatially carried out discrete, optical distance is calculated using ray tracing method, the information such as bond material, buildup factor carry out the calculating of equation group coefficient, and backstepping goes out source strength；Then close rate calculating is carried out to detector position, by the way that measured value and calculated value are carried out linear regression analysis, calculates the key parameters such as standard deviation, slope, intercept, and then calculate quality factor to weigh the acceptable degree of each result of calculation；Propose the Weighted Iterative Methods simultaneously, the error that the larger detector of reduction uncertainty is introduced, using the mode of iteration, above steps may be repeated multiple times until quality factor reach pre-set value, obtains desired radiation source intensity information.
Description
Technical field
The present invention relates to the computational methods of radiation source intensity in nuclear power plant and system, and in particular to a kind of nuclear power plant's point source line
The recombination radiation source strength backstepping method of source body source combination and the recombination radiation source strength backstepping system of point source line source body source combination.
Background technology
The active region of the radioactivity of nuclear power plant fuel assembly in pressure vessel, radiation source mainly by fission product,
Actinides and activating product composition.In system operation, radiation source is with coolant flow through primary Ioops main system (including pressure
Container, main pump, voltage-stablizer, main pipeline etc.), chemical vessel control system etc., Distribution of radiation source is in cooling agent and relevant device table
Face.Radiation source radioactivity itself is strong, and the dosage suffered by daily routines of the staff when nuclear power plant normally runs accounts for year total agent
20% or so of amount, and during nuclear power station overhaul, the dosage suffered by staff will account for the 80% of year accumulated dose, in core
Mainly radioactive dose is reduced during power plant's overhaul by shortening staff in the residence time of radiation area.
Distribution of radiation source is especially passed through by prolonged than wide using with after overhaul according to engineering in nuclear power plant
Test and be increasingly difficult to be inferred to the radiation intensity of each position radiation source, so in very multidata calculating, especially foundation
In the calculating of radiation source intensity, because it is difficult to obtain accurate Back ground Information and greatly affected accuracy and practicality, together
When, in the case that current protective equipment and means are not very complete at home, also make it that the illuminated risk of staff is big
Big increase.
In the prior art, it is necessary to when calculating radiation source intensity, Sources term analysis method typically be used, first, according to radioactive material
The generation of matter and disappearance approach determine its generation item (as flowed into item, decay produces item etc.) and disappearance item (such as filtering item, leakage item
Deng), and clearly every physical model, nucleon concentration balance equation is then set up to radioactive substance according to above-mentioned items
(group), last simultaneous equations (group) solve, but there is substantial amounts of simplification and approximate calculation in these calculating process, so its
As a result it is often larger with actual value gap, in practical application in the presence of many obstacles, in addition, in view of radiation source in itself
Complicated geometry, radionuclide accurate information are difficult to obtain inside the harm that is caused to human body, nuclear power plant, nuclear power plant is visited
When surveying the factors such as the uncertainty of device measured value, the above method is problematic in that in terms of security, accuracy, it would be highly desirable to improved
Or propose new radiation source intensity acquiring way.
For these reasons, the present inventor furthers investigate to the method for existing calculating source strength information, rule of thumb,
Part radioactive components can be reduced to point source or be reduced to line source in usual nuclear power plant, and a such as thermal valve can be reduced to one
Individual point source a, pipeline can be reduced to a point source or multiple point sources, can also be simplified to a line source, can also be reduced to
Simple body source, such as spheroid source, cylinder source, cuboid source, and sliding-model control can be carried out to line source, body source, from
And source strength backstepping is carried out according to the information after sliding-model control and obtains radiation source intensity information, it can solve the problem that so as to design one kind
The recombination radiation source strength backstepping method of nuclear power plant's point source line source body source combination of above mentioned problem and answering for point source line source body source combination
Close radiation source intensity backstepping system.
The content of the invention
In order to overcome above mentioned problem, present inventor has performed studying with keen determination, a kind of nuclear power plant's point source line source body source is designed
The recombination radiation source strength backstepping method of combination and the recombination radiation source strength backstepping system of point source line source body source combination, this method and be
System can obtain body inside nuclear power plant under complex geometry space structure in a steady stream in the case where fully ensureing human body radiation safety
Strong data；In this method, detector is placed in the precalculated position in nuclear power plant, and is also placed in the position with shielded spy
Device is surveyed, and then obtains the average energy that radiation source releases gamma ray；In addition, being additionally provided with multiple monitoring nuclear powers in nuclear power plant
The detector of factory's radiation value, to obtain the close rate of part sampling site, the side combined using Point- kernel integral and weighted least-squares method
Formula, while normalization radiation source intensity is spatially carried out into discrete, to judge to release per individual sources using ray tracing method γ
Ray walks distance and calculates optical distance space, and the information such as bond material, buildup factor carries out equation group coefficient
Calculate, and then backstepping goes out source strength；Then the calculated value to close rate at detector position is obtained, measured value and calculated value are carried out
Linear regression analysis is handled, and obtains the key parameters such as standard deviation, slope, intercept, and then obtain that the product of physical meaning can be represented
Prime factor, the quality factor can weigh the acceptable degree of each result of calculation；A kind of the Weighted Iterative Methods are proposed simultaneously, are reduced
The error that the larger detector of uncertainty is introduced, using the mode of iteration, above steps may be repeated multiple times until quality factor are met
Default condition, and then the uncertainty of desired radiation source intensity and radiation field result is obtained, so as to complete the present invention.
In particular it is object of the present invention to provide following aspect：
(1) a kind of recombination radiation source strength backstepping method of nuclear power plant's point source line source body source combination, it is characterised in that this method
Comprise the following steps：
Step one, the close rate D in nuclear power plant is detected with detector1,D2,D3…Di,
Step 2, according to the close rate information detected, sets up super containing radiation source intensity as shown in following formula (one)
Determine equation group,
Wherein, the coefficient matrix a of the over-determined systemsi,jObtained by following formula (two) and (three),
In formula (three), when radiation source is point source, p=0, L=1, M=1, N=1；When radiation source is line source, p=
1, M=1, N=1；When radiation source is body source, p=1；
Step 3, radiation source intensity information is obtained by the over-determined systems in least square method calculation procedure two, described
Radiation source intensity is following formula (four)
Sj,0=(aj,i·ai,j)-1·aj,i·Di(4)
Wherein, DiRepresent the close rate that i-th of detector detection is obtained；J represents the number of radiation source；M represents radiation source
The maximum that number can reach；SjRepresent the intensity of j-th of radiation source；Sj,0Represent j-th of spoke that initial calculation is not iterated
Penetrate the intensity in source；ai,jCoefficient matrix is represented, is dose response coefficient of j-th of radiation source to i-th of detector；BD(E,L(μ
(E),r0→rp) buildup factor is represented, it is E and L (μ (E), r0→rp) function；L(μ(E),r0→rp) optical distance is represented, be
μ (E) and r0→rpFunction；μ (E) represents section/linear attenuation coefficient；r0→rpRepresent radiation source to the distance of sensing point；C
(E) fluence-dose conversion factor is represented, is E function；E represents energy, is the gamma rays that radiation source is sent in nuclear power plant
Average energy；Discrete source strength is represented, L, M and N therein represent body source discrete rear three coordinates on three-dimensional coordinate respectively
Discrete label on axle；
Preferably, after step 3, methods described also comprises the following steps,
Step 4, according to the close rate at the radiation source intensity information calculating detector position obtained in step 3, D '1,
D′2,D′3…D′i；
The close rate information at detector position that step 5, the close rate information detected to detector and calculating are obtained
Linear fit, the linear equation of the both sides relation after being fitted are carried out, and then obtains fitting parameter, the fitting parameter bag
Include：Average uncertainty, the goodness of fit and corresponding weight matrix；
Step 6, over-determined systems of the new weight matrix iteration obtained in step 5 into step 2 are added
The overdetermined equation of power, and then repeat step two, step 3 and step 4, until obtaining desired radiation source intensity information；
Wherein, D 'iThe close rate at i-th of detector position that expression is calculated.
(2) the recombination radiation source strength backstepping method of nuclear power plant's point source line source body source combination according to above-mentioned (1), it is special
Levy and be, the discrete source strengthObtained by following formula (five)：
Wherein, when radiation source is body source, SU(L)、SVAnd S (M)W(N) after representing that body source is discrete on three-dimensional coordinate respectively
The source strength weight factor in the source strength weight factor and W coordinate axle in source strength weight factor, V reference axis on U coordinate axle；
Preferably, when the body source is cylinder source, SU(L)、SVAnd S (M)W(N) following formula (six), (seven) are passed through respectively
(8) obtain：
Wherein, η1,1、η1,2、η2,1、η2,2、η3,1And η3,2Cosine distribution constant is all represented, R represents the radius in cylinder source, Z
The height in cylinder source is represented,Represent the angle in cylinder source；
Preferably, when the body source is spheroid source, SU(L)、SVAnd S (M)W(N) respectively by following formula (nine), (ten) and
(11) obtain：
Wherein, η1,1、η1,2、η2,1、η2,2、η3,1And η3,2Cosine distribution constant is all represented, R represents the radius in spheroid source, θ tables
Show the level angle in spheroid source,Represent the vertical angle in spheroid source；
Preferably, when the body source is cuboid source, SU(L)、SVAnd S (M)W(N) following formula (12), (ten are passed through respectively
Three) obtained with (14)：
Wherein, η1,1、η1,2、η2,1、η2,2、η3,1And η3,2Cosine distribution constant is all represented, x represents the length in cuboid source, z
The height in cuboid source is represented, y represents the width in cuboid source.
(3) the recombination radiation source strength backstepping method of nuclear power plant's point source line source body source combination according to above-mentioned (1), it is special
Levy and be, the average energy E of the gamma rays sent for radiation source in the nuclear power plant, its measuring method includes following sub-step
Suddenly：
Sub-step 1, chooses precalculated position inside nuclear power plant, and the precalculated position is t apart from the distance of radiation source, pre- at this
Placement location detector is positioned, the close rate I that the detector is detected is collected0,
Sub-step 2, fetches the detector, is coated outside it and the precalculated position is placed on after screen layer, collect institute
State the close rate I that detector is detected；
Or, the detector is fetched, shield is placed in precalculated position, then the detector is placed on shield
It is interior, collect the close rate I that the detector is detected；
Sub-step 3, the I and I obtained according to sub-step 1 and step 20, clad or shielding are calculated by following formula (15)
The mass attentuation coefficient μ of body,
I/I0=BDe-μt(15)
Sub-step 4, according to the result of calculation of sub-step 3, obtains the average energy E for the gamma rays that radiation source is sent.
(4) the recombination radiation source strength backstepping method of nuclear power plant's point source line source body source combination according to above-mentioned (1), it is special
Levy and be, calculating the method for the optical distance L includes following sub-step,
Sub-step a, tracking gamma ray walks process from radiation source to sensing point, and record gamma ray passes through radiation area
The order in domain,
Sub-step b, calculates the distance of each radiation areas respectively, with reference to the linear taper system of each radiation areas material
Number, finally obtains total optical distance L.
(5) the recombination radiation source strength backstepping method of nuclear power plant's point source line source body source combination according to above-mentioned (1), it is special
Levy and be, using the over-determined systems in Least Square in Processing step 2, and obtain the process of radiation source intensity information and include
Following sub-step：
Sub-step 3-1, by over-determined systemsAX=b is expressed as with the form of matrix；
Sub-step 3-2, seeks the normal equation A of the matrixTAX=ATB, i.e. X=(ATA)-1ATb；
Sub-step 3-3, with the triangle decomposition method solution normal equation of symmetrical matrix, remembers G=ATA, wherein, G is symmetrical matrix；
Sub-step 3-4, G=LDL is solved using triangle decomposition methodT, wherein L is small triangular matrix, and D is diagonal matrix；
Sub-step 3-5, solves lower triangular matrix equation group:LY1=ATb；
Sub-step 3-6, solves diagonal matrix equation group：DY2=Y1；
Sub-step 3-7, solves upper triangular matrix equation group：LTX=Y2。
(6) the recombination radiation source strength backstepping method of nuclear power plant's point source line source body source combination according to above-mentioned (2), it is special
Levy and be, in step 5, linear fit is carried out by following formula (16),
Wherein,Represent the close rate of estimation；The slope of estimation is represented, The intercept of estimation is represented,
N represents the maximum that detector number i can reach,Close rate is averaged at the detector position that expression is calculated
Value,Represent the average value for the close rate that detector is detected.
(7) the recombination radiation source strength backstepping method of nuclear power plant's point source line source body source combination according to above-mentioned (6), it is special
Levy and be, in step 5, weighting function is obtained according to uncertainty, then weight matrix W, the power are obtained by weighting function
Weight matrix W is obtained by following formula (17),
Wherein, f represents to be fitted uncertainty, Average fit uncertainty is represented,
fiRepresent the fitting uncertainty of i-th of detector position；；Represent weighting function.
(8) the recombination radiation source strength backstepping method of nuclear power plant's point source line source body source combination according to above-mentioned (6), it is special
Levy and be,
In step 6, work as Si＞ 0, and quality factor M stops weighted iteration, and output radiation source strength when reaching maximum
Information is spent, the radiation source intensity information now exported is the desired radiation source intensity information；
Wherein, quality factor a M, the quality factor M are all correspondingly made available when performing step 6 every time and passes through following formula
(18) are obtained,
Wherein, R2Represent the goodness of fit,
(9) a kind of recombination radiation source strength backstepping system of nuclear power plant's point source line source body source combination, it is characterised in that the system
Recombination radiation source strength backstepping method for performing nuclear power plant's point source line source body source combination described in above-mentioned (1)-(8).
(10) the recombination radiation source strength backstepping system of nuclear power plant's point source line source body source combination according to above-mentioned (9), its
It is characterised by, the system includes detector, gamma rays average energy computing module and radiation source intensity computing module；
The detector has multiple, including precalculated position detector and nuclear power plant's radiation value monitoring detector,
The precalculated position detector is arranged in nuclear power plant radiation areas the pre-determined bit that distance is determined between radiation source
Put, and dismountable screen layer is optionally coated with outside the precalculated position detector；
The precalculated position detector be used for will the radiation dose rate information transmission that detect to gamma rays average energy
Computing module,
Nuclear power plant's radiation value monitoring detector is distributed in the radiation areas of nuclear power plant, for that will separately detect
Nuclear power plant's middle dosage rate information transmission to radiation source intensity computing module,
The gamma rays average energy computing module is used for the average energy E for calculating gamma rays,
The radiation source intensity computing module is used to calculate radiation source intensity in nuclear power plant.
The present invention have the advantage that including：
(1) the recombination radiation source strength backstepping method combined according to nuclear power plant's point source line source body source for providing of the present invention can be
In the case of fully ensureing human body radiation safety, body inside nuclear power plant under complex geometry space structure strong data in a steady stream are obtained；
(2) the recombination radiation source strength backstepping method that the nuclear power plant's point source line source body source provided according to the present invention is combined passes through many
Secondary iterative calculation, it is ensured that strong information is more adjacent to actual value to the body finally given in a steady stream, with very high engineering application value.
Brief description of the drawings
Fig. 1 shows the overall workflow figure according to a kind of preferred embodiment of the invention.
Embodiment
Below by drawings and examples, the present invention is described in more detail.Illustrated by these, the features of the present invention
It will be become more apparent from clearly with advantage.
Special word " exemplary " is meant " being used as example, embodiment or illustrative " herein.Here as " exemplary "
Illustrated any embodiment should not necessarily be construed as preferred or advantageous over other embodiments.
The recombination radiation source strength backstepping method that the nuclear power plant's point source line source body source provided according to the present invention is combined, this method bag
Include following steps：
Step one, the close rate information D that the detector in power plant is detected is received1,D2,D3…Di, it is above-mentioned many in order to detect
Individual close rate in the present invention, can place multiple detectors, it is necessary to use multiple detectors into power plant, can also direct profit
With the detector existed in nuclear power plant, the detector existed in nuclear power plant is nuclear power plant's radiation value monitoring detector,
It can be combined with using above two mode, be for the status requirement where above-mentioned detector：Radiation source and the position it
Between there is no a shield, heretofore described close rate is radiation dose rate.In the present invention, the quantity of the detector is more than nuclear power
The quantity of radiation source in factory.
Step 2, according to the close rate information detected, sets up the over-determined systems containing radiation source intensity, the overdetermination
Equation group is following formula (one),
Step 3, radiation source intensity information is obtained by the over-determined systems in least square method calculation procedure two, described
Radiation source intensity is following formula (four)
The coefficient matrix a of the over-determined systemsi,jBe by body source on radiation space coordinate it is discrete after by following formula
(2) obtained with (three),
In formula (three), when radiation source is point source, p=0, L=1, M=1, N=1；When radiation source is line source, p=
1, M=1, N=1；When radiation source is body source, p=1；I.e. described radiation source can be body source, can be line source, can also be
Point source.
In the present invention, due to needing the region for calculating radiation source intensity many, it is necessary to the radiation of measuring and calculating in a nuclear power plant
Source also has a lot, in different regions or for different radiation sources, and selection can be caused to be intended chemical conversion point source or line
Source or body source, and can be calculated by above-mentioned formula (three), when radiation source is point source, p=0, L=1, M=1, N
=1；When radiation source is line source, p=1, M=1, N=1；When the radiation source is body source, p=1.When radiation source is point source,
Discrete processes can not be done to radiation source, i.e.,
After step 3, have been able to obtain the strength information of radiation source, but the strength information is possible and inadequate
Accurately, so continuing to calculate by following step, to obtain the radiation source intensity information for more pressing close to actual value；
Step 4, according to the close rate at the radiation source intensity information calculating detector position obtained in step 3, D '1,
D′2,D′3…D′i；
The close rate information at detector position that step 5, the close rate information detected to detector and calculating are obtained
Linear fit, the linear equation of the both sides relation after being fitted are carried out, and then obtains fitting parameter, the fitting parameter bag
Include：Average uncertainty, the goodness of fit and corresponding weight matrix；Heretofore described weight matrix can be interior weight square
Battle array or outer weight matrix, its preparation method are consistent, and uncertainty is not by system if difference is outer weight matrix
Calculate what is obtained, but the detector error range inputted by operator's means.
Step 6, over-determined systems of the weight matrix iteration obtained in step 5 into step 2 are weighted
Overdetermined equation, and then repeat step two, step 3 and step 4, until obtaining desired radiation source intensity information；
In the present invention, D represents the close rate that detector is detected；DiRepresent the close rate that i-th of detector detection is obtained；
I represents the number of detector；J represents the number of radiation source, and m represents the maximum that radiation source number can reach；S represents radiation source
Intensity；SjRepresent the intensity of j-th of radiation source；Sj,0Represent the intensity for j-th of radiation source that initial calculation is not iterated；
ai,jCoefficient matrix is represented, is dose response coefficient of j-th of radiation source to i-th of detector, point source pair is represented in the present invention
The response coefficient of detector also illustrates that line source and body source after discrete to the response coefficient of detector；BD(E,L(μ(E),r0→rp) table
Show buildup factor, be E and L (μ (E), r0→rp) function；L(μ(E),r0→rp) optical distance is represented, it is μ (E) and r0→rp
Function, i.e. optical distance is the function of energy and actual range；μ (E) represents linear attenuation coefficient；r0→rpRepresent radiation source
To the distance of sensing point；C (E) represents fluence-dose conversion factor, is E function；E represents energy, is radiation source in nuclear power plant
The average energy of the gamma rays sent；D′iThe close rate at i-th of detector position that expression is calculated；Represent from
Source strength is dissipated, L, M and N therein represent discrete label of the body source on three-dimensional coordinate in discrete rear three reference axis respectively.Wherein,
The sensing point represents the position of detector, is more precisely the position that radiation information is received on detector.
Heretofore described discrete source strengthObtained by following formula (five)：
Wherein, when radiation source is body source, SU(L)、SVAnd S (M)W(N) after representing that body source is discrete on three-dimensional coordinate respectively
The source strength weight factor in the source strength weight factor and W coordinate axle in source strength weight factor, V reference axis on U coordinate axle；
Preferably, when the body source is cylinder source, SU(L)、SVAnd S (M)W(N) following formula (six), (seven) are passed through respectively
(8) obtain：
Wherein, η1,1、η1,2、η2,1、η2,2、η3,1And η3,2All represent cosine distribution constant, the cosine distribution constant acquiescence
Value is zero, can be configured according to actual conditions, and Z represents the height in cylinder source,The angle in cylinder source is represented, it is described
The angle in cylinder source is exactly the anglec of rotation of cylinder；That is,
Preferably, when the body source is spheroid source, SU(L)、SVAnd S (M)W(N) respectively by following formula (nine), (ten) and
(11) obtain：
Wherein, η1,1、η1,2、η2,1、η2,2、η3,1And η3,2All represent cosine distribution constant, the cosine distribution constant acquiescence
Value is zero, can be configured according to actual conditions, and R represents the radius in spheroid source, and θ represents the level angle in spheroid source,Table
Show the vertical angle in spheroid source；That is,
Preferably, when the body source is cuboid source, SU(L)、SVAnd S (M)W(N) following formula (12), (ten are passed through respectively
Three) obtained with (14)：
Wherein, η1,1、η1,2、η2,1、η2,2、η3,1And η3,2All represent cosine distribution constant, the cosine distribution constant acquiescence
Value is zero, can be configured according to actual conditions, and x represents the length in cuboid source, and z represents the height in cuboid source, and y is represented
The width in cuboid source；I.e.
Preferably, when the radiation source is line source,
That is,
Wherein, XLCoordinate after expression line source is discrete；Cosine constant is represented, the numerical value can be taking human as input, default value
For 0；L represents discrete number, i.e., line source is divided into the number being divided into when several pieces carry out discrete calculation.
Heretofore described buildup factor is professional term commonly used in the art, can refer to generally containing in this area
Justice is explained and calculated, and its calculation formula generally is provided in the present invention as follows：
Wherein KxFitting formula it is as follows：
K (E, x)=cxa+d[tanh(x/Xk-2)-tanh(-2)]/[1-tanh(-2)]；
Wherein E is photon energy, MeV；xFor source point to the distance for calculating point；B be accumulation at mean free path because
Son；a,c,d,XkFor empirical parameter, when tiring out the selection of factor coefficient, it can select to use log difference mode, i.e.,：
a(Ea)={ a (E1)·[log(E2)-log(Ea)]+a(E2)·[log(Ea)-log(E1)]}/[log(E2)-log
(E1)]
In one preferred embodiment, the average energy E for the gamma rays that radiation source is sent in the nuclear power plant
Measuring method includes following sub-step：
Sub-step 1, chooses precalculated position inside nuclear power plant, and the precalculated position is t apart from the distance of radiation source, pre- at this
Placement location detector is positioned, the close rate I that the detector is detected is collected0,
Sub-step 2, fetches the detector, is coated outside it and the precalculated position is placed on after screen layer, collect institute
State the close rate I that detector is detected；
Or, the detector is fetched, shield is placed in precalculated position, then the detector is placed on shield
It is interior, collect the close rate I that the detector is detected；
Sub-step 3, the I and I obtained according to sub-step 1 and step 20, clad or shielding are calculated by following formula (15)
The mass attentuation coefficient μ of body,
I/I0=BDe-μt(15)
Sub-step 4, according to the result of calculation of sub-step 3, tables look-up and obtains the average energy for the gamma rays that radiation source is sent
E.The table tabled look-up can be material section table, and the token is loaded in ANSI/ANS 6.4.3, " Gamma-ray
Attenuation Coefficients and Buildup Factor for Engineering Materials”,
American Nuclear Society, 16-67 pages of 1991..In the present invention, all use emittance, all with above-mentioned
Average energy is calculated, if its capacity volume variance of different zones is larger in nuclear power plant, it may be considered that the region is individually calculated, i.e., single
Solely measuring and calculating average energy, individually calculates radiation source intensity.
In one preferred embodiment, calculating the method for the optical distance L includes following sub-step, sub-step a,
Track gamma ray and walk process from radiation source to sensing point, record gamma ray passes through the order of radiation areas, that is, passed through
Ray tracking method calculates radiation source to sensing point apart from r0→rp, wherein r0The position of radiation source is represented, sensing point is represented
Position rp.Sub-step b, calculates the distance of each radiation areas respectively, with reference to the linear taper coefficient of each radiation areas material,
Finally obtain total optical distance L.
Specifically, gamma-rays is calculated when walking distance, describes space with combinatorial geometry method, and by different medium
Space is divided into different regions.Obtain respectively the distance between the intersection point of gamma ray and each basic body and entrance Di and
With outlet the distance between Do.Obtain all basic body numbering plus and minus with "+" and "-", the process in each region
It may include six following steps,
(1) the starting point r of every line0Region Ipstart determination：
If not having "-" basic body in some region, then in the region, all "+" basic bodies must all have been fulfilled for
Point r0In all "+" basic bodies, then it is considered that the initiation region of ray is the region；If having in the region
"-" basic body, then all "+" basic bodies must all are fulfilled for starting point r in the region0In all "+" basic bodies, and
And all "-" basic bodies must all are fulfilled for the starting point r not comprising this ray0, then the initiation region for thinking ray is the area
Domain.
(2) the terminal r of every linepRegion Ipend determination：
If likewise, not having "-" basic body in some region, then in the region, all "+" basic bodies are all necessary
Meet terminal rpIn all "+" basic bodies, then it is considered that the termination area of ray is the region；If the region
In have "-" basic body, then all "+" basic bodies must all are fulfilled for terminal r in the regionpPositioned at all "+" basic bodies
In, and all "-" basic bodies must all are fulfilled for the terminal r not comprising this rayp, then the termination area for thinking ray is
The region.
(3) the starting point r of every line0Determination of the corresponding regional export in region number apart from Zo：
If do not have in gamma-rays initiation region number the basic body conveying ends of "+" all in "-" basic body, initiation region away from
It is with a distance from the outlet of the gamma-rays initiation region from reckling in Do.If there is "-" basic body in gamma-rays initiation region, rise first
The basic body conveying end for owning "+" in beginning region is minimum in Do, then own "-" basic bodies take import in Di most
Small, take the outlet distance that both maximums are the gamma-rays initiation region.
(4) the numbering IP in each region that ray passes through determination：
Terminal is not under outermost areas case, if not having "-" basic body in regional number, and adjacent subarea domain is carried out first
Judgement, for all "+" basic bodies, basic body import distance is less than or equal to the import distance in region and less than basic body
Outlet apart from when (Di<=Zin<Do), the region is the adjacent area in a upper region, obtains corresponding zone number IP；
If there is "-" basic body in gamma-rays regional number, for all "+" basic bodies, basic body import distance is less than or equal to region
Import distance and the outlet distance (Di for being less than basic body<=Zin<Do), and to all "-" basic bodies, basic body import
Distance is more than zone inlet distance or basic body outlet distance is less than or equal to zone inlet distance (Di>Zin or Do<=Zin)
When, the region is the adjacent area in a upper region, obtains corresponding zone number IP.
(5) import in each region that ray passes through is apart from Zi and exports the determination apart from Zo：
If not having "-" basic body in the above-mentioned adjacent area obtained, the regional export distance is the basic body of all "+"
Outlet is minimum in Do, and the import distance in the region is the outlet distance in a upper region；If the above-mentioned adjacent region obtained
There is "-" basic body in domain, first obtain the basic body conveying end of all "+" reckling in Do, obtaining the basic of all "-"
Body import reckling in Di, then takes the outlet distance that both maximums are the region, and the import distance in the region is
For the outlet distance in a upper region.
(6) terminal finds all basic body numbering aa of outermost layer under outermost areas case, first, for region
Middle "+" basic body includes basic body aa, when "-" basic body does not include basic body aa region, looks for whether there is ray process
In region "-" import of basic body distance is more than the import distance (Di (k, minus (i, m)) in region>Zi (k, n)) "-" base
Body, if it does, regional export distance takes all "-" basic body import recklings in Di, if it does not, region goes out
Mouth distance is ray length.
Trace into rpPoint region IPend and radiation exit distance be equal to ray length when terminate.So as to obtain γ
Ray walks distance.
The number of times of ray crossing area is carried out again and walks the calculating of distance every time：
If the crossing area numbering of ray is not 0, then the gamma-ray distance of walking in the region is equal to zone inlet distance
Cut regional export distance, gamma-rays walks number of times and plus 1；If gamma-ray crossing area numbering is 0, stop tracking.
γ section μ are obtained using the material of γ mass attentuation coefficients and Region Mediumn；
Then by above-mentioned record gamma-rays by the process of walking during region, the optical distance in each region is obtained respectively
Sum again, i.e.,：Wherein, N represents the quantity of radiation areas, and the quantity is main
Determined by factory building internal environment.
In one preferred embodiment, using the over-determined systems in Least Square in Processing step 2, and obtain
The process of radiation source intensity information includes following sub-step：
Sub-step 3-1, by over-determined systemsAX=b is expressed as with the form of matrix；
Sub-step 3-2, seeks the normal equation A of the matrixTAX=ATB, i.e. X=(ATA)-1ATb；
Sub-step 3-3, with the triangle decomposition method solution normal equation of symmetrical matrix, remembers G=ATA, wherein, G is symmetrical matrix；
Sub-step 3-4, G=LDL is solved using triangle decomposition methodT, wherein L is small triangular matrix, and D is diagonal matrix；
Sub-step 3-5, solves lower triangular matrix equation group:LY1=ATb；
Sub-step 3-6, solves diagonal matrix equation group：DY2=Y1；
Sub-step 3-7, solves upper triangular matrix equation group：LTX=Y2。
Wherein, X=(ATA)-1ATB withIt is corresponding, pass through the sub-step
3-1 obtains the evaluation of radiation source intensity to sub-step 3-7, and heretofore described least square method is general in this area
Overdetermined equation calculation method.
In one preferred embodiment, in step 5, linear fit is carried out by following formula (16),
Wherein,Represent the close rate of estimation；The slope of estimation is represented, Represent cutting for estimation
Away from,
N represents the maximum that detector number i can reach,Close rate is averaged at the detector position that expression is calculated
Value,Represent the average value for the close rate that detector is detected.
In one preferred embodiment, after linear fit, the average not true of linear fit is also respectively obtained
Fixed degree, the goodness of fit, quality factor, weighting function and corresponding weight matrix, the quality factor represent current iteration calculating
Confidence level.In step 5, weighting function is obtained according to uncertainty, then by weighting function acquisition weight matrix W, it is described
Weight matrix W is obtained by following formula (17),
Wherein, f represents to be fitted uncertainty,fiRepresent the fitting uncertainty of i-th of detector position；Average fit uncertainty is represented, Represent weighting function.
In one preferred embodiment, in step 6, the judgement of the desired radiation source intensity information is obtained
Condition is to work as SiDuring ＞ 0, and quality factor M reaches maximum, that is, works as Si＞ 0, and quality factor M stop when reaching maximum plus
Iteration, and output radiation source strength information are weighed, the radiation source intensity information is exactly the desired radiation source intensity finally given,
It is closest to the radiation source intensity of actual value.
It is an object of the invention to obtain the radiation source intensity closest to actual value, and the radiation source intensity that step 3 is obtained
Reliability ratio it is relatively low, its error between actual value can be than larger, so the accuracy in order to improve the numerical value, that is, obtain
Closest to the radiation source intensity of actual value, step 4 is given to the weighted iteration process of step 6 in the present invention, and finally set
The condition of iteration ends is determined, to reduce workload as far as possible in the case of ensureing that result is accurate, has shortened the activity duration, improve number
According to the efficiency of acquisition.According to the criterion of above-mentioned the Weighted Iterative Methods and iteration ends.In addition, the radiation obtained in the present invention
Source strength than Sources term analysis method obtain radiation source intensity it is more accurate, more press close to actual value, ensure that acquisition value with
Actual value is within an order of magnitude.In one preferred embodiment, one is all correspondingly made available when performing step 6 every time
Individual quality factor M, the quality factor M is obtained by following formula (18),
Wherein, R2Represent the goodness of fit,
In one preferred embodiment, over-determined systemsMatrix form see below formula (19)
Wherein, ε represents the error that each detector is introduced；Consider caused by physics meaning, actually each sensing point
Error may be considered caused by radiation source, then above-mentioned equation simplification is following formula (20),
And then it can be found that, coefficient matrix ai,jDose response coefficient of j-th of radiation source to i-th of detector is equivalent to,
Wherein, the dose response coefficient of detector is calculated using Point- kernel integral technology, and the Point- kernel integral technology meter is this area
Middle conventional computational methods.
The recombination radiation source strength backstepping system that a kind of nuclear power plant's point source line source body source provided according to the present invention is combined, this is
Unite for the recombination radiation source strength backstepping method for performing the above nuclear power plant's point source line source body source combination of the present invention.
Preferably, the system includes detector, gamma rays average energy computing module and radiation source intensity computing module；
The detector has multiple, including precalculated position detector and nuclear power plant's radiation value monitoring detector,
The precalculated position detector is arranged in nuclear power plant radiation areas the pre-determined bit that distance is determined between radiation source
Put, and dismountable screen layer is optionally coated with outside the precalculated position detector；The precalculated position distance radiation
The distance in source can occur in follow-up calculating as known quantity；
The precalculated position detector be used for will the radiation dose rate information transmission that detect to gamma rays average energy
Computing module, to calculate gamma rays average energy；
Nuclear power plant's radiation value monitoring detector is distributed in the radiation areas of nuclear power plant, respectively the institute in the present invention
The key position stated, for the nuclear power plant's middle dosage rate information transmission that will separately detect to radiation source intensity computing module,
The gamma rays average energy computing module is used for the average energy E for calculating gamma rays,
The radiation source intensity computing module is used to calculate radiation source intensity in nuclear power plant.
Experimental example：
Using NB281 rooms in No. 1 unit nuclear island of Daya Bay nuclear power plant as experimental subjects, the room is in nuclear island control zone
For placing the place that radioactive wastewater collecting vessel is housed, wastewater collection bucket is a hydrostatic column, inner radiation fluid supply
It is 0.7586E+10MeV/cm by force3.s (or 4.2898E+14/s).The top half of the hydrostatic column is reduced to 1 point
Source and 1 line source, the latter half are reduced to 1 cylinder source, and a spy is set every 50cm in wastewater collection bucket center section
Survey device, totally five detectors, the probe value that each detector is obtained be respectively 2.032mSv/hr, 0.685mSv/hr,
0.255mSv/hr, 0.1446mSv/hr, 0.0929mSv/hr, are the D in the present invention1,D2,D3,D4,D5, carried according to the present invention
The average energy acquisition methods and system of confession obtain average energy for 1.3MeV, the source strength backstepping method that is provided using the present invention and
System, obtains point source source strength for 1.0746E+14/s, and line source source strength is 1.0762E+14/s, and body is 2.1371E+14/ by force in a steady stream
s。
It was found from final result, the radiation intensity actual value of obtained point source line source body strong sum and the radiation source in a steady stream
It is basically identical, it is possible to illustrate that the method and system of the invention provided result in the radiation source intensity letter of actual value
Breath.
Above in association with preferred embodiment the present invention is described, but these embodiments are only exemplary
, only play illustrative effect.On this basis, a variety of replacements and improvement can be carried out to the present invention, these each fall within this
In the protection domain of invention.
Claims (10)
1. a kind of recombination radiation source strength backstepping method of nuclear power plant's point source line source body source combination, it is characterised in that this method includes
Following steps：
Step one, the close rate D in nuclear power plant is detected with detector1,D2,D3…Di；
Step 2, according to the close rate information detected, sets up the overdetermination side containing radiation source intensity as shown in following formula (one)
Journey group,
Wherein, the coefficient matrix a of the over-determined systemsi,jObtained by following formula (two) and (three),
In formula (three), when radiation source is point source, p=0, L=1, M=1, N=1；When radiation source is line source, p=1, M=
1, N=1；When radiation source is body source, p=1；
Step 3, by the over-determined systems in Least Square in Processing step 2, obtains the radiation source intensity as shown in following formula (four)
Spend information,
Sj,0=(aj,i·ai,j)-1·aj,i·Di(4)；
Wherein, DiRepresent the close rate that i-th of detector detection is obtained；J represents the number of radiation source；M represents radiation source number energy
The maximum reached；SjRepresent the intensity of j-th of radiation source；Sj,0Represent j-th of radiation source that initial calculation is not iterated
Intensity；ai,jCoefficient matrix is represented, is dose response coefficient of j-th of radiation source to i-th of detector；BD(E,L(μ(E),r0
→rp) buildup factor is represented, it is E and L (μ (E), r0→rp) function；L(μ(E),r0→rp) represent optical distance, be μ (E) and
r0→rpFunction；μ (E) represents section/linear attenuation coefficient；r0→rpRepresent radiation source to the distance of sensing point；C (E) is represented
Fluence-dose conversion factor, is E function；E represents energy, is the average energy of the gamma rays that radiation source is sent in nuclear power plant
Amount；Discrete source strength is represented, L, M and N therein represent body source on three-dimensional coordinate in discrete rear three reference axis respectively
Discrete label；
Preferably, after step 3, methods described also comprises the following steps,
Step 4, according to the close rate at the radiation source intensity information calculating detector position obtained in step 3, D '1,D′2,
D′3…D′i；
Step 5, the close rate information detected to detector and the close rate information calculated at obtained detector position are carried out
Linear fit, the linear equation of the both sides relation after being fitted, and then fitting parameter is obtained, the fitting parameter includes：It is flat
Equal uncertainty, the goodness of fit and corresponding weight matrix；
Step 6, by over-determined systems of the weight matrix iteration obtained in step 5 into step 2, the overdetermination weighted
Equation, and then repeat step two, step 3 and step 4, until obtaining desired radiation source intensity information；
Wherein, D 'iThe close rate at i-th of detector position that expression is calculated.
2. the recombination radiation source strength backstepping method of nuclear power plant's point source line source body source combination according to claim 1, its feature
It is, the discrete source strengthObtained by following formula (five)：
Wherein, when radiation source is body source, SU(L)、SVAnd S (M)W(N) represent that body source discrete rear U on three-dimensional coordinate is sat respectively
The source strength weight factor in the source strength weight factor and W coordinate axle in source strength weight factor, V reference axis on parameter；
Preferably, when the body source is cylinder source, SU(L)、SVAnd S (M)W(N) respectively by following formula (six), (seven) and
(8) obtain：
Wherein, η1,1、η1,2、η2,1、η2,2、η3,1And η3,2Cosine distribution constant is all represented, R represents the radius in cylinder source, and Z is represented
The height in cylinder source,Represent the angle in cylinder source；
Preferably, when the body source is spheroid source, SU(L)、SVAnd S (M)W(N) following formula (nine), (ten) and (ten are passed through respectively
One) obtain：
Wherein, η1,1、η1,2、η2,1、η2,2、η3,1And η3,2Cosine distribution constant is all represented, R represents the radius in spheroid source, and θ represents ball
The level angle in body source,Represent the vertical angle in spheroid source；
Preferably, when the body source is cuboid source, SU(L)、SVAnd S (M)W(N) following formula (12), (13) are passed through respectively
(14) obtain：
Wherein, η1,1、η1,2、η2,1、η2,2、η3,1And η3,2Cosine distribution constant is all represented, x represents the length in cuboid source, and z is represented
The height in cuboid source, y represents the width in cuboid source.
3. the recombination radiation source strength backstepping method of nuclear power plant's point source line source body source combination according to claim 1, its feature
It is, the average energy E of the gamma rays sent for radiation source in the nuclear power plant, its measuring method includes following sub-step
Suddenly：
Sub-step 1, chooses precalculated position inside nuclear power plant, and the precalculated position is t apart from the distance of radiation source, in the pre-determined bit
Placement location detector, collects the close rate I that the detector is detected0,
Sub-step 2, fetches the detector, is coated outside it and the precalculated position is placed on after screen layer, collects described visit
Survey the close rate I that device is detected；
Or, the detector is fetched, shield is placed in precalculated position, then the detector is placed in shield, receive
Collect the close rate I that the detector is detected；
Sub-step 3, the I and I obtained according to sub-step 1 and step 20, the matter of clad or shield is calculated by following formula (15)
Measure attenuation coefficient mu,
I/I0=BDe-μt(15)
Sub-step 4, according to the result of calculation of sub-step 3, obtains the average energy E for the gamma rays that radiation source is sent.
4. the recombination radiation source strength backstepping method of nuclear power plant's point source line source body source combination according to claim 1, its feature
It is, calculating the method for the optical distance L includes following sub-step,
Sub-step a, tracking gamma ray walks process from radiation source to sensing point, and record gamma ray passes through radiation areas
Sequentially,
Sub-step b, calculates the distance of each radiation areas respectively, with reference to the linear taper coefficient of each radiation areas material, most
Total optical distance L is obtained afterwards.
5. the recombination radiation source strength backstepping method of nuclear power plant's point source line source body source combination according to claim 1, its feature
It is, using the over-determined systems in Least Square in Processing step 2, and obtains the process of radiation source intensity information including such as
Lower sub-step：
Sub-step 3-1, by over-determined systemsAX=b is expressed as with the form of matrix；
Sub-step 3-2, seeks the normal equation A of the matrixTAX=ATB, i.e. X=(ATA)-1ATb；
Sub-step 3-3, with the triangle decomposition method solution normal equation of symmetrical matrix, remembers G=ATA, wherein, G is symmetrical matrix；
Sub-step 3-4, G=LDL is solved using triangle decomposition methodT, wherein L is small triangular matrix, and D is diagonal matrix；
Sub-step 3-5, solves lower triangular matrix equation group:LY1=ATb；
Sub-step 3-6, solves diagonal matrix equation group：DY2=Y1；
Sub-step 3-7, solves upper triangular matrix equation group：LTX=Y2。
6. the recombination radiation source strength backstepping method of nuclear power plant's point source line source body source combination according to claim 1, its feature
It is, in step 5, linear fit is carried out by following formula (16),
Wherein,Represent the close rate of estimation；The slope of estimation is represented, Represent estimation
Intercept,
N represents the maximum that detector number i can reach,The average value of close rate at the detector position that expression is calculated,
Represent the average value for the close rate that detector is detected.
7. the recombination radiation source strength backstepping method of nuclear power plant's point source line source body source combination according to claim 6, its feature
It is, in step 5, weighting function is obtained according to uncertainty, then weight matrix W, the weight are obtained by weighting function
Matrix W is obtained by following formula (17),
Wherein, f represents to be fitted uncertainty, Average fit uncertainty is represented,fi
Represent the fitting uncertainty of i-th of detector position；Represent weighting function.
8. the recombination radiation source strength backstepping method of nuclear power plant's point source line source body source combination according to claim 6, its feature
It is,
In step 6, work as Si＞ 0, and quality factor M stops weighted iteration when reaching maximum, and output radiation source strength is believed
Breath, the radiation source intensity information now exported is the desired radiation source intensity information；
Wherein, quality factor a M, the quality factor M are all correspondingly made available when performing step 6 every time and passes through following formula (ten
Eight) obtain,
Wherein, R2Represent the goodness of fit,
9. a kind of recombination radiation source strength backstepping system of nuclear power plant's point source line source body source combination, it is characterised in that the system is used for
Perform claim requires the recombination radiation source strength backstepping method of nuclear power plant's point source line source body source combination described in 1-8.
10. the recombination radiation source strength backstepping system of nuclear power plant's point source line source body source combination according to claim 9, its feature
It is, the system includes detector, gamma rays average energy computing module and radiation source intensity computing module；
The detector has multiple, including precalculated position detector and nuclear power plant's radiation value monitoring detector,
The precalculated position detector is arranged in nuclear power plant radiation areas the precalculated position that distance is determined between radiation source, and
Dismountable screen layer is optionally coated with outside the precalculated position detector；
Radiation dose rate information transmission to the gamma rays average energy that the precalculated position detector is used to detect is calculated
Module,
Nuclear power plant's radiation value monitoring detector is distributed in the radiation areas of nuclear power plant, for by the nuclear power separately detected
Factory's middle dosage rate information transmission to radiation source intensity computing module,
The gamma rays average energy computing module is used for the average energy E for calculating gamma rays,
The radiation source intensity computing module is used to calculate radiation source intensity in nuclear power plant.
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|---|---|---|---|---|
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Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2002077667A1 (en) * | 2001-03-23 | 2002-10-03 | Koninklijke Philips Electronics N.V. | Method of determining the quantity of radiation absorbed by a radiation sensor |
| CN103592035A (en) * | 2013-11-08 | 2014-02-19 | 中国运载火箭技术研究院 | Method for testing infrared focal plane detector component dosage rate |
| CN103675890A (en) * | 2012-09-21 | 2014-03-26 | 日立民用电子株式会社 | Radiation measurement apparatus and radiation measurement method |
-
2016
- 2016-04-12 CN CN201610224104.XA patent/CN107292762B/en not_active Expired - Fee Related
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2002077667A1 (en) * | 2001-03-23 | 2002-10-03 | Koninklijke Philips Electronics N.V. | Method of determining the quantity of radiation absorbed by a radiation sensor |
| CN103675890A (en) * | 2012-09-21 | 2014-03-26 | 日立民用电子株式会社 | Radiation measurement apparatus and radiation measurement method |
| CN103592035A (en) * | 2013-11-08 | 2014-02-19 | 中国运载火箭技术研究院 | Method for testing infrared focal plane detector component dosage rate |
Non-Patent Citations (2)
| Title |
|---|
| 徐加强等: "上海光源光束线站BL18U轫致辐射剂量的计算与测量", 《核技术》 * |
| 李德鑫等: "基于逆绕射抛物方程法的辐射源定位技术研究", 《电波科学学报》 * |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111950924A (en) * | 2020-08-21 | 2020-11-17 | 成都希盟泰克科技发展有限公司 | Nuclear power plant progress calculation method based on intelligent algorithm |
| CN111950924B (en) * | 2020-08-21 | 2023-06-02 | 成都希盟泰克科技发展有限公司 | Nuclear power plant progress calculation method based on intelligent algorithm |
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