CN107195342B - A method of measurement nuclear power plant's nucleic activity distribution - Google Patents
A method of measurement nuclear power plant's nucleic activity distribution Download PDFInfo
- Publication number
- CN107195342B CN107195342B CN201710216323.8A CN201710216323A CN107195342B CN 107195342 B CN107195342 B CN 107195342B CN 201710216323 A CN201710216323 A CN 201710216323A CN 107195342 B CN107195342 B CN 107195342B
- Authority
- CN
- China
- Prior art keywords
- point
- nucleic
- impact
- currently assigned
- energy
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/017—Inspection or maintenance of pipe-lines or tubes in nuclear installations
-
- G—PHYSICS
- G06—COMPUTING; CALCULATING OR COUNTING
- G06T—IMAGE DATA PROCESSING OR GENERATION, IN GENERAL
- G06T17/00—Three dimensional [3D] modelling, e.g. data description of 3D objects
-
- G—PHYSICS
- G06—COMPUTING; CALCULATING OR COUNTING
- G06T—IMAGE DATA PROCESSING OR GENERATION, IN GENERAL
- G06T2210/00—Indexing scheme for image generation or computer graphics
- G06T2210/56—Particle system, point based geometry or rendering
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Computer Graphics (AREA)
- Geometry (AREA)
- Software Systems (AREA)
- General Physics & Mathematics (AREA)
- Theoretical Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Measurement Of Radiation (AREA)
Abstract
The present invention provides a kind of method of measurement nuclear power plant's nucleic activity distribution, nucleic and measurement data are specified including obtaining detector, enter preset mode using actual measurement measurement data as current continuous data, obtains single-row vector and its element number that the actual measurement probability right value of each specified nucleic is lined up；Specify element number that the classification of nucleic is mock up flat single-row vector corresponding with its as recurring number using each, according to geometrical model circulating analog detector, it obtains the measurement data simulated every time and enters preset mode and handle, obtain the analog probability weighted value that each specifies nucleic when it is modeled every time and the homotype matrix formed by analog probability weighted value；The single-row vector and its corresponding homotype matrix that nucleic is specified according to each calculate the activity distribution of each specified nucleic.Implement the present invention, can overcome the shortcomings of existing radiation " hot spot " detection means, accurately measures out workshop radiation " hot spot " activity distribution situation.
Description
Technical field
The present invention relates to technical field of nuclear radiation measurement more particularly to a kind of sides of measurement nuclear power plant's nucleic activity distribution
Method.
Background technique
With the gradually aging of active service nuclear power plant, China, in reactor internal pipeline activation corrosion product specific position by
Year accumulation, forms gamma emitter, and this kind of radiation " hot spot " is being increased year by year, so that during overhaul suffered by staff
Dose of radiation also increases year by year, causes the problem of controlling collective's dose of radiation more prominent.
Whether ray, or the radiation field emerged by calculating " hot spot " are weakened to optimize operation by the method for shielding
Path all be unable to do without the accurate measurement to " hot spot ".But measurement radiation " hot spot " and common " find and lose radioactive source " are no
Same: firstly, " looking for source " problem usually can be seen as point source, and nucleic type is single, is carried out into mature gamma camera
Position as that can find radioactive source, however workshop radiation " hot spot " usually all accumulates in inside pipeline or equipment, has one
Fixed geometry and size cannot be considered as point source, and nucleic complicated composition, and gamma energy range is wide, to detector
Energy resolution require it is high；Secondly, workshop radiation " hot spot " is related to three big key parameters: positionEnergyAnd work
DegreeThese three parameters not instead of three scalars, the function that three independents variable are constituted, being equivalent to will find out by x × y × z × i
The matrix that × j unknown number forms.
In the prior art, gamma ray spectrometer, cellular type γ camera (including orifice type and coding cellular type) and Compton are generallyd use
Scattering imaging type gamma camera radiates " hot spot " activity distribution situation to measure workshop.But although inventors have found that gamma ray spectrometer
Power spectrum can be surveyed and provide energy and intensity (i.e. i × j matrix), but do not have position resolution, survey is all position radiation
The mixing resultant in source；Cellular type γ camera can provide two-dimensional position and intensity (i.e. x × z × j matrix), but on the one hand because usually adopting
With scintillator detector, energy resolution is generally inferior to 7%, is unable to effective district pyrene element, and survey be all nucleic mixing
Intensity, the another aspect visual field are generally less than 60 °, must just shoot respectively, take towards all multi-angles when measuring larger range space
When it is laborious；Although Compton scatter imaging formula gamma camera can provide two-dimensional position, energy and intensity (i.e. x × z × i simultaneously
× j matrix), and it is not necessarily to collimator, visual angle is up to 360 °, but the result being imaged is only capable of presenting with the two dimensional form at longitude and latitude angle,
The transmitted intensity picture being superimposed on optical photograph is shot, quantitative measurment when not can solve radiation " hot spot " by material blocks
The problem of source strength.
Therefore, a kind of method for needing measurement workshop radiation " hot spot " activity distribution, can overcome existing radiation " hot spot "
The deficiency of detection means accurately measures out workshop radiation " hot spot " activity distribution situation.
Summary of the invention
The technical problem to be solved by the embodiment of the invention is that providing a kind of side of measurement nuclear power plant's nucleic activity distribution
Method can overcome the shortcomings of existing radiation " hot spot " detection means, accurately measure out workshop radiation " hot spot " activity distribution situation,
Reflect that nuclear power plant's radiation " hot spot " is related to three-dimensional position, energy and intensity simultaneously and (has given the x of three big key parameters
× y × z × i × j matrix).
In order to solve the above-mentioned technical problem, the embodiment of the invention provides a kind of sides of measurement nuclear power plant's nucleic activity distribution
Method, which comprises
Obtain specifies nucleic and gained to correspond to and switch to inside gamma events after surveying nuclear power plant's radioactive source to be measured by detector
The measurement data of the point of impact, and the actual measurement measurement data got is entered into preset mode as current continuous data and is fallen into a trap
It calculates, and specifies the classification of nucleic as unit of account using each, respectively obtain the actual measurement probability right value of each specified nucleic,
It further obtains each specified nucleic and single-row vector composed by actual measurement probability right value and corresponding single-row vector is corresponded to as it
Element number.
Using the geometrical model for covering card program and establishing space and the detector locating for radioactive source to be measured in the nuclear power plant,
And with each specify the classification of nucleic by mock up flat and its correspond to and be made of actual measurement probability right value the member of single-row vector
Plain number is recurring number, detects nuclear power plant's radiation to be measured by detector described in the geometrical model circulating analog for covering card building
Behind source, the measurement data simulated when gamma events obtained by the detector switch to the point of impact every time is obtained respectively, and by each institute
It states the analogue measurement data that get and enters in the preset mode respectively as current continuous data and calculate, obtain each and refer to
Determine analog probability weighted value of the nucleic when it is modeled every time, is further modeled same specified nucleic every time
Analog probability weighted value is that column vector forms its corresponding homotype matrix；Wherein, the actual measurement measurement data and the simulation are surveyed
Amount data include three-dimensional position, hit time and the energy deposition of the point of impact.
According to each obtained specify nucleic as its correspond to actual measurement probability right value composed by single-row vector and
Corresponding to analog probability weighted value by it is that column vector is formed by homotype matrix, and by equation Ax=b, it is specified to calculate each
The activity of nucleic is distributed；Wherein, A is that correspond to analog probability weighted value by it be that column vector is formed by together to each specified nucleic
Type matrix, b are each specified nucleic single-row vector as composed by its correspondence actual measurement probability right value, and x is specified for each
The vector that be solved activity value of the nucleic in each space lattice confined is lined up.
Wherein, the current continuous data enters the specific steps that calculate in the preset mode and includes:
Determine the classification of corresponding currently assigned nucleic when current continuous data enters calculating, and according to currently assigned nucleic
Classification obtain the gamma energy of currently assigned nucleic in preset nucleic characteristic gamma ray energy scale, and according to
The gamma energy of the preset energy resolution ratio of the detector and the currently assigned nucleic, determines currently assigned nucleic
Energy window range in power spectrum；
According to the hit time of each point of impact in current continuous data, to all hits in the current continuous data
Point carries out primary screening, obtains the point of impact for meeting default combination condition and its combination of the corresponding point of impact, and work as according to described
Each in the gamma energy of preceding specified nucleic and its corresponding energy window range and the current continuous data is hit
The energy deposition of point, carries out postsearch screening, life needed for obtaining currently assigned nucleic to the point of impact that primary screening obtains respectively
Midpoint and its combination of the corresponding point of impact, and further according to the gamma energy of the currently assigned nucleic and its corresponding
Point of impact combination, obtains the Compton scattering point and photoelectric absorption point of currently assigned nucleic；
It is deposited, is determined in currently assigned nucleic according to the three-dimensional position of each point of impact in current continuous data and energy
The three-dimensional position and energy of Compton scattering point and photoelectric absorption point deposition in all point of impact combinations, and with currently assigned nucleic
Interior any group of point of impact combination is unit, according in currently assigned nucleic in each group of point of impact combination Compton scattering point and
The three-dimensional position and energy of photoelectric absorption point deposit and the gamma energy of currently assigned nucleic, in currently assigned nucleic
Any point of impact combination progress circular conical surface is virtual, obtains combining with the point of impact each in currently assigned nucleic corresponding virtual
Circular conical surface；Wherein, each described virtual circular conical surface is to correspond to Compton scattering in point of impact combination in currently assigned nucleic
The three-dimensional position of point be vertex, with correspond in currently assigned nucleic the point of impact combine in Compton scattering point to opposite photoelectric absorption
Point vector be axis and correspond to using in currently assigned nucleic the point of impact combination in specifically Compton scattering angle as semi-cone angle structure
It builds；Specific Compton scattering angle is to be corresponded in currently assigned nucleic to hit by it in each described virtual circular conical surface
The energy deposition of Compton scattering point and the gamma energy of currently assigned nucleic determine in point combination；
Each described virtual circular conical surface progress discretization traversal processing obtained in currently assigned nucleic, and according to
Discretization traversal processing as a result, in the cube grid that preset three-dimensional space is divided, filter out storage have it is currently assigned
The cube grid of virtual circular conical surface and its corresponding quantity for storing virtual circular conical surface in nucleic, and further according to each institute
Screening cube grid stores the quantity of virtual circular conical surface, and obtaining currently assigned nucleic corresponding to current continuous data is the reality
It is the analogue measurement number that actual measurement probability right value or currently assigned nucleic when surveying measurement data, which correspond to current continuous data,
According to when analog probability weighted value；Wherein, the preset three-dimensional space is by constructing radioactive source to be measured in the nuclear power plant
The three-dimensional cartesian coordinate system that locating space matches is realized, including multiple cube nets with identical specifiable lattice size
Lattice.
Wherein, in the current continuous data of the basis each point of impact the hit time, to the current continuous data
In all points of impact carry out primary screenings, obtain the point of impact for meeting default combination condition and its combination of the corresponding point of impact, and
According in the gamma energy of the currently assigned nucleic and its corresponding energy window range and the current continuous data
The energy of each point of impact deposits, and carries out postsearch screening to the point of impact that primary screening obtains respectively, obtains currently assigned core
The required point of impact of element and its combination of the corresponding point of impact, and further according to the gamma energy of the currently assigned nucleic
And its combination of the corresponding point of impact, the step of obtaining the Compton scattering point and photoelectric absorption point of currently assigned nucleic, specifically wrap
It includes:
To any combination of two of the point of impact in the current continuous data, and according to each in the current continuous data
The hit time of a point of impact screens two points of impact of all any combination, retains and meet the preset group out
The point of impact of conjunction condition and its combination of formation；
According to the energy deposition of each point of impact in the current continuous data, the energy for retaining the point of impact is determined
The energy for depositing, and calculating every group of point of impact in the corresponding combination of the reservation point of impact deposits the sum of cumulative；
According to the energy window range of the currently assigned nucleic and calculated retain every group of point of impact in combination
Energy deposition is the sum of cumulative, screens to reservations combination, obtains currently assigned nucleic and meet preset energy comparing condition
Combination and its corresponding required point of impact；
According to the gamma energy of the currently assigned nucleic and its corresponding combination, it is set in currently assigned nucleic
When gamma energy is greater than or equal to preset threshold, energy deposits big hit in the corresponding any combination of currently assigned nucleic
Point is that deposit the small point of impact be photoelectric absorption point for Compton scattering point, energy；Or it is set in the gal of currently assigned nucleic
When horse ray energy is less than the preset threshold, it is equal to deposit the big point of impact for energy in the corresponding any combination of currently assigned nucleic
Depositing the small point of impact for photoelectric absorption point, energy is Compton scattering point.
Wherein, the default combination condition is that any hit time interval for retaining two points of impact among combination should be less than
The detector response time, and two points of impact all have uniqueness among any reservation combination.
Wherein, the energy that the preset energy compares that condition is two points of impact in any reservation combination deposits the sum of cumulative
It should be located within the scope of the energy window of the currently assigned nucleic.
Wherein, specific Compton scattering angle passes through formula in each described described virtual circular conical surfaceTo realize；Wherein, θ is Compton scattering angle, E1For any life in currently assigned nucleic
The energy deposition of Compton scattering point, E in the combination of midpoint0For the gamma energy of currently assigned nucleic, mec2For photon matter
Amount, is constant.
Wherein, described that each described virtual circular conical surface obtained in currently assigned nucleic is carried out at discretization traversal
Reason, and according to discretization traversal processing as a result, filtering out storage has in the cube grid that preset three-dimensional space is divided
The cube grid of virtual circular conical surface and its corresponding quantity for storing virtual circular conical surface in currently assigned nucleic, and further basis
Each screened cube grid stores the quantity of virtual circular conical surface, obtains currently assigned nucleic corresponding to current continuous data
For it is described actual measurement measurement data when actual measurement probability right value or currently assigned nucleic correspond to current continuous data be the mould
The step of analog probability weighted value when quasi- measurement data, specifically includes:
All cube grids in the preset three-dimensional space are assigned a value of 0；
First is executed each described virtual circular conical surface obtained in currently assigned nucleic to recirculate after traversal, is continued
Second is executed each described virtual circular conical surface obtained in currently assigned nucleic to recirculate traversal, is filtered out two and is recirculated
Storage has the cube grid of virtual circular conical surface in currently assigned nucleic and counts each screened cube grid after traversal
The quantity of the middle virtual circular conical surface of storage；Wherein, described first recirculate traversal using imaginary circles cone element length as amplitude variations,
And set amplitude variations value and carry out being incremented by traversal with specific amplitude increment since 0, until set amplitude variations value exceeds
Until the boundary of the preset three-dimensional space；Described second recirculates traversal when being respectively radius of circle with each amplitude variations value
Corresponding central angle is angle variables, and set angle variate-value carries out being incremented by traversal with special angle increment since 0, directly
Until set angle variables value is 2 π；Wherein, the specific amplitude increment is set as cube grid specifiable lattice size
1/10-1/3 one；It is corresponding in cube grid specifiable lattice size 1/10-1/5 that the special angle increment is set as arc length
Its central angle for the moment；
The quantity that each screened cube grid is counted, and will be obtained simultaneously multiplied by a given value
Product, which respectively corresponds, assigns each screened cube grid；
When detecting current continuous data is the actual measurement measurement data, each by the imparting is screened cube
Actual measurement probability right value of the product of volume mesh as currently assigned nucleic；
When detecting current continuous data is the analogue measurement data, each by the imparting is screened cube
Analog probability weighted value of the product of volume mesh as currently assigned nucleic.
Wherein, the three-dimensional position X of the point of impact, Y-direction pass through in the actual measurement measurement data and the analogue measurement
The pixel serial number of the detector determines, Z-direction be using the electronics drift duration of nuclear electronics record gamma events come
It determines.
Wherein, the actual measurement measurement data is by the way that the detector to be placed in locating for radioactive source to be measured described in nuclear power plant
Outside space and in the range of described 1 to 10 meter of radioactive source to be measured, opens and detect described radioactive source to be measured 1 to 120 minute
And it obtains.
Wherein, the classification of the specified nucleic includes58Co、60Co、110mAg、124Sb、137Cs、51Cr、54Mn、59Fe、95Zr
、95Nb、134Cs、131I。
The implementation of the embodiments of the present invention has the following beneficial effects:
1, in embodiments of the present invention, resulting actual measurement measures number either after detector direct detection radioactive source to be measured
According to or analog prober detect resulting analogue measurement data after radioactive source to be measured, the two includes that the point of impact (radiates
" hot spot ", nucleic) three-dimensional position (x × y × z), energy deposition (i), and the two be involved in preset mode calculate come
Activity (j) distribution situation of nucleic out, thus set up nuclear power plant radiation " hot spot " simultaneously with three-dimensional position, energy and intensity phase
It closes (giving x × y × z × i × j matrix of three big key parameters), overcomes existing radiation " hot spot " detection means not
Foot；
2, analogue measurement data obtained by after in embodiments of the present invention, detecting radioactive source to be measured as analog prober are corresponding
Analog probability weighted value be formed by homotype matrix to correct resulting actual measurement after detector direct detection radioactive source to be measured and survey
The actual measurement probability right value of amount data is formed by single-row vector, and the activity distribution situation of the nucleic obtained is more accurate, to mention
High computational accuracy.
Detailed description of the invention
In order to more clearly explain the embodiment of the invention or the technical proposal in the existing technology, to embodiment or will show below
There is attached drawing needed in technical description to be briefly described, it should be apparent that, the accompanying drawings in the following description is only this
Some embodiments of invention, for those of ordinary skill in the art, without any creative labor, according to
These attached drawings obtain other attached drawings and still fall within scope of the invention.
Fig. 1 is a kind of flow chart of the method for measurement nuclear power plant's nucleic activity distribution provided in an embodiment of the present invention.
Specific embodiment
To make the object, technical solutions and advantages of the present invention clearer, the present invention is made into one below in conjunction with attached drawing
Step ground detailed description.
As shown in Figure 1, in the embodiment of the present invention, a kind of method of the measurement nuclear power plant nucleic activity distribution provided, institute
The method of stating includes:
Step S1, obtaining gained after surveying nuclear power plant's radioactive source to be measured by detector specifies nucleic and gained to correspond to gamma thing
Switch to the measurement data of the point of impact inside part, and enters the actual measurement measurement data got as current continuous data in advance
If calculating in mode, and specify the classification of nucleic as unit of account using each, respectively obtains the actual measurement of each specified nucleic
Probability right value further obtains each specified nucleic as it and corresponds to single-row vector composed by actual measurement probability right value and right
Answer the element number of single-row vector；
Detailed process is, first before step S1, the sensitive gamma detector of three-dimensional position is selected to wait for survey nuclear power plant
Survey radioactive source, this kind of detector be able to record each hit detector and generate energy deposition gamma events, provide its
The three-dimensional position of the point of impact, hit time and energy deposition inside detector.In one embodiment, this kind of detector is usually adopted
With cadmium-zinc-teiluride (CdZnTe) semiconductor array detector, can also be made of other materials.
The three-dimensional position of this kind of detector record point of impact can use but be not limited to following methods: the position of X, Y-direction
It is determined, i.e., is realized by the way that detector sensitive area is carried out pixelation, typical way by the pixel serial number of detector
It is that anode is divided into latticed, common cathode, the location information of X, Y-direction is converted into using anode serial number；Z-direction is benefit
It is determined with the electronics drift duration of nuclear electronics record gamma events, i.e., records the electric float of each event using nuclear electronics
Duration is moved, the depth information of Z-direction is converted into, allows for the three-dimensional of the point of impact of each gamma events inside detector in this way
Location information can be read and be used.
The sensitive gamma detector of three-dimensional position is placed in space locating for nuclear power plant's radioactive source to be measured, i.e., may such as be contained
In the workshop for radiating " hot spot " (radioactive source i.e. to be measured), because " hot spot " is generally deposited on the positions such as pipeline or valve, and distance
In the range of 1 to 10 meter of radioactive source to be measured, opens and detect radioactive source to be measured 1 to 120 minute, record each gamma events pair
It should switch to three-dimensional position, hit time and the energy deposition of the point of impact.These information form gamma events data set, Ke Yi
The data being recorded are transmitted to computer at any time in detection process, total data can also be packaged again after detection and be passed
It is defeated.It can be seen that the measured data that computer is got includes three-dimensional position, hit time and the energy deposition of the point of impact.
Secondly, before step S1, it is also necessary to establish the feature of each specified nucleic of actual measurement nuclear power plant's radioactive source to be measured
Gamma energy table (the characteristic gamma ray energy scale of i.e. pre-set specified nucleic), wherein the classification of specified nucleic
Including but not limited to58Co、60Co、110mAg、124Sb、137Cs、51Cr、54Mn、59Fe、95Zr、95Nb、134Cs、131I.It is each in selection
When the characteristic gamma ray of the specified nucleic of kind is as measurement object, following strategy is mainly followed:
(1) specify nucleic gamma ray energy will be located at detector response range in (preferentially select 250-1500keV,
Next selects 50-250keV and 1500-2000keV)；(2) preferential, the ray for specifying the emission probability of nucleic gamma ray high
Energy is biggish preferential；(3) according to the energy resolution of detector, avoid with fall into oblivion peak (511keV), backscattering peak (~
Energy 180keV) got too close to；(4) it for the nucleic for specifying nucleic to have a plurality of gamma ray alternative, generally selects 1 γ and penetrates
Line is as main survey object, and 1-3 gamma ray of reselection is as verification.
In one embodiment, according to above-mentioned strategy, the characteristic gamma ray of specified nucleic is selected, as shown in table 1 below:
Table 1
| Nucleic | Main survey gamma energy E0 | Gamma ray for verification |
| 58Co | 810.8keV | Nothing |
| 60Co | 1332.5keV | 1173.2keV |
| 110mAg | 884.7keV | 657.8keV、937.5keV、1384.3keV |
| 124Sb | 1691.0keV | 602.7keV |
| 137Cs | 661.7keV | Nothing |
| 51Cr | 320.1keV | Nothing |
| 54Mn | 834.8keV | Nothing |
| 59Fe | 1099.2keV | 1291.6keV |
| 95Zr | 724.2keV | 756.7keV |
| 95Nb | 765.8keV | Nothing |
| 134Cs | 795.84keV | 604.7keV |
| 131I | 364.48keV | Nothing |
Finally, each specified nucleic, actual measurement measurement data and preset nucleic feature for will being obtained before step S1
Gamma energy table all imports in computer, and will survey measurement data as continuous data and pass through internal preset mode meter
It calculates, to obtain the actual measurement probability right value of each nucleic and its to be correspondingly formed the element number of single-row vector.
In embodiments of the present invention, actual measurement measurement data enters the process tool of preset mode calculating as current continuous data
Body is as follows:
Step S11, the classification of corresponding currently assigned nucleic when current continuous data enters calculating is determined, and according to current
The classification of specified nucleic obtains the gamma ray energy of currently assigned nucleic in preset nucleic characteristic gamma ray energy scale
Amount, and according to the preset energy resolution ratio of the detector and the gamma energy of the currently assigned nucleic, determination is worked as
Energy window range of the preceding specified nucleic in power spectrum；
Specifically, corresponding gamma energy is found according to the classification of currently assigned nucleic, according to the default of detector
Energy resolution (representative value 1%-3%) converses energy window of the currently assigned nucleic in power spectrum in table 1.Energy window
Width can take 2.54 times of the all-round peak width FWHM of detector, can also take other width.Formula is as follows: above and below energy window
Boundary=E0± 1.27FWHM=E0±1.27·R·E0；
In one embodiment, it is into the currently assigned nucleic of calculating58Co, characteristic gamma ray ENERGY E0In upper table
It is found in 1 as 810.8keV, detector is the energy resolution R=2% of the sensitive gamma detector of three-dimensional position at this time, is conversed
Nucleic to be measured58Energy window range of the Co in power spectrum is 790.2keV-831.4keV.
Step S12, according to the hit time of each point of impact in current continuous data, in the current continuous data
All points of impact carry out primary screening, obtain the point of impact for meeting default combination condition and its combination of the corresponding point of impact, and root
According to every in the gamma energy of the currently assigned nucleic and its corresponding energy window range and the current continuous data
The energy deposition of one point of impact, carries out postsearch screening to the point of impact that primary screening obtains respectively, obtains currently assigned nucleic
The required point of impact and its combination of the corresponding point of impact, and further according to the gamma energy of the currently assigned nucleic and
Its corresponding point of impact combination, obtains the Compton scattering point and photoelectric absorption point of currently assigned nucleic；
Specifically, step S121, to any combination of two of the point of impact in the current continuous data, and worked as according to described
The hit time of each point of impact in preceding continuous data screens two points of impact of all any combination, retains
Meet the point of impact of the default combination condition and its combination of formation；Wherein, the default combination condition is any reservation group
The hit time interval of two points of impact should be less than the detector response time among conjunction, and two among any reservation combination
The point of impact all has uniqueness；
It is understood that step S121 is to carry out " double point of impact events " screening to current continuous data, method is first
The hit time for judging each point of impact is less than detector response time for the interval of any two point of impact hit time
, all it is considered as and is caused by the same gammaphoton, thus establishes the association in time of each point of impact, it follows that
Which point of impact is caused by the same gammaphoton.The event that one gammaphoton generates 2 points of impact just is known as " double
Point of impact event ", all such events are retained, remaining is rejected more or less than the event of 2 points of impact.
Step S122, it is deposited according to the energy of each point of impact in the current continuous data, determines the reservation life
The energy at midpoint deposits, and the energy deposition for calculating every group of point of impact in the corresponding combination of the reservation point of impact is the sum of cumulative；
It is understood that step S122 is to two lives in the combination that " double point of impact events " remains in step S121
The energy at midpoint deposits summation, so as to postsearch screening, obtains the point of impact that currently assigned nucleic needs.
Step S123, according to every group in the calculated reservation combination of the energy window range of the currently assigned nucleic and institute
The energy deposition of the point of impact is the sum of cumulative, combines and screens to reservations, obtains currently assigned nucleic and meet preset energy
The combination of comparison condition and its corresponding required point of impact；Wherein, the preset energy comparison condition is in any reservation combination
The energy deposition of two points of impact is the sum of cumulative to be located within the scope of the energy window of the currently assigned nucleic；
It is understood that the energy deposition that step S123 is used to two points of impact in judgement reservation combination one by one adds up it
Whether it is located within the scope of the energy window of currently assigned nucleic；If it is, continuing to remain as can imaging event；If
It is no, then it abandons.
Step S124, it according to the gamma energy of the currently assigned nucleic and its corresponding combination, is set in current
When the gamma energy of specified nucleic is greater than or equal to preset threshold, energy is heavy in the corresponding any combination of currently assigned nucleic
The big point of impact of product is that deposit the small point of impact be photoelectric absorption point for Compton scattering point, energy；Or it is set in current finger
When determining the gamma energy of nucleic and being less than the preset threshold, energy deposition is big in the corresponding any combination of currently assigned nucleic
The point of impact be that deposit the small point of impact be Compton scattering point for photoelectric absorption point, energy.
It is understood that step S124 is used to determine the gamma energy E if currently assigned nucleic0>=default
Energy in any combination in currently assigned nucleic is then deposited the biggish point of impact and dissipated labeled as Compton by threshold value (such as 400keV)
Exit point, energy deposit the lesser point of impact and are labeled as photoelectric absorption point, if conversely, then determining that the gamma of currently assigned nucleic is penetrated
Heat input E0Energy in any combination in currently assigned nucleic then will be deposited biggish hit by < preset threshold (such as 400keV)
Point is labeled as photoelectric absorption point, and energy deposits the lesser point of impact and is labeled as Compton scattering point.
Step S13, it is deposited according to the three-dimensional position of each point of impact in current continuous data and energy, determines and currently refer to
Determine in nucleic the three-dimensional position and energy of Compton scattering point and photoelectric absorption point deposition in the combination of all points of impact, and with current
Any group of point of impact combination in specified nucleic is unit, according to Compton in each group of point of impact combination in currently assigned nucleic
The gamma energy of the three-dimensional position and energy of scattering point and photoelectric absorption point deposition and currently assigned nucleic, to currently finger
Determine any point of impact combination in nucleic and carries out that circular conical surface is virtual, and it is right to obtain combining with the point of impact each in currently assigned nucleic
The virtual circular conical surface answered；Wherein, each described virtual circular conical surface is to correspond to health in point of impact combination in currently assigned nucleic
The three-dimensional position of general scattering point be vertex, with correspond in currently assigned nucleic the point of impact combine in Compton scattering point to opposite
The vector of photoelectric absorption point is axis and specifically Compton scattering angle is in point of impact combination to correspond in currently assigned nucleic
Semi-cone angle is built-up；Specific Compton scattering angle is to correspond to currently assigned core by it in each described virtual circular conical surface
The energy deposition of Compton scattering point and the gamma energy of currently assigned nucleic determine in point of impact combination in element；
Specifically, determining in currently assigned nucleic three of Compton scattering point and photoelectric absorption point in all points of impact combinations
Position and energy deposition are tieed up, and as unit of any group of point of impact combination in currently assigned nucleic, with Compton scattering point
Three-dimensional position is vertex, using the vector of Compton scattering point to opposite photoelectric absorption point as axis, with specific Compton scattering angle θ
For semi-cone angle, virtual circular conical surface is constructed in space.
Wherein, specific Compton scattering angle θ passes through formulaTo realize；Wherein, θ
For Compton scattering angle, E1For the energy deposition of Compton scattering point in the point of impact any in currently assigned nucleic combination, E0To work as
The gamma energy of preceding specified nucleic, mec2It is constant for photon quality.
Step S14, each described virtual circular conical surface obtained in currently assigned nucleic is carried out at discretization traversal
Reason, and according to discretization traversal processing as a result, filtering out storage has in the cube grid that preset three-dimensional space is divided
The cube grid of virtual circular conical surface and its corresponding quantity for storing virtual circular conical surface in currently assigned nucleic, and further basis
Each screened cube grid stores the quantity of virtual circular conical surface, obtains currently assigned nucleic corresponding to current continuous data
For it is described actual measurement measurement data when actual measurement probability right value or currently assigned nucleic correspond to current continuous data be the mould
Analog probability weighted value when quasi- measurement data；Wherein, the preset three-dimensional space be by construct in the nuclear power plant to
The three-dimensional cartesian coordinate system that space locating for radioactive source matches is surveyed to realize, including multiple vertical with identical specifiable lattice size
Cube grid.
Specifically, all cube grids in the preset three-dimensional space are assigned a value of 0；
First is executed each described virtual circular conical surface obtained in currently assigned nucleic to recirculate after traversal, is continued
Second is executed each described virtual circular conical surface obtained in currently assigned nucleic to recirculate traversal, is filtered out two and is recirculated
Storage has the cube grid of virtual circular conical surface in currently assigned nucleic and counts each screened cube grid after traversal
The middle quantity traversed by virtual circular conical surface；Wherein, described first traversal is recirculated using imaginary circles cone element length as amplitude
Variable, and set amplitude variations value and carry out being incremented by traversal with specific amplitude increment since 0, until set amplitude variations value
Until boundary beyond the preset three-dimensional space；Described second recirculates traversal with each amplitude variations value respectively circle half
Corresponding central angle is angle variables when diameter, and set angle variate-value is carried out incremental time since 0 with special angle increment
It goes through, until set angle variables value is 2 π；Wherein, the specific amplitude increment is set as cube grid specifiable lattice
The one of the 1/10-1/3 of size；It is corresponding in cube grid specifiable lattice size 1/ that the special angle increment is set as arc length
Its central angle for the moment；
By each screened cube grid by the traversed quantity of virtual circular conical surface simultaneously multiplied by a given value,
And obtained product is respectively corresponded and assigns each screened cube grid.Then, by each institute of the imparting
Screen actual measurement probability right value of the product of cube grid as currently assigned nucleic.
It should be noted that preset three-dimensional space is matched by space locating for radioactive source to be measured in building nuclear power plant
Three-dimensional cartesian coordinate system realize, including multiple cube grids with identical specifiable lattice size, the specifiable lattice ruler
It is very little to can be 1-10cm, it is also possible to other sizes.Size of mesh opening determines the space essence of final source strength distribution measuring results
Fineness, therefore the setting of size of mesh opening will be with the typical component in space to be measured (for example, may deposit the pipe of " hot spot " in workshop
Road) geometric scale be adapted.
It is understood that recirculate by above-mentioned two, each virtual circular conical surface translates into computer program can be with
The series of points of traversal.For the point that each is traversed, judge which cube grid it belongs to according to its three-dimensional position,
And add up a upper value (i.e. virtual circular conical surface quantity is multiplied by a value) for the corresponding probability right of the grid, this value can be consolidated
It is set to 1 or other numerical value, is also possible to variable related with traversal point position.
After actual measurement probability right value determines, although it reflects the probability that its corresponding grid contains the nucleic, this
Probability value is not yet equal to the nucleic activity that the grid contains, but the two has unique conversion relation in the measurements, needs to pass through spy
Efficiency calibration is surveyed to determine.Therefore, after step s 14, need for the actual measurement probability right value of currently assigned nucleic to be converted into
Element number is lined up and counted to the form of three-dimensional matrice, in the form of single-row vector singly by element so as to subsequent
The realization of detection efficiency calibration.
Step S2, the several of space locating for radioactive source to be measured and the detector in the nuclear power plant are established using covering card program
What model, and with each specify the classification of nucleic for mock up flat and its correspondence from actual measurement probability right value form it is single-row to
The element number of amount is recurring number, detects nuclear power plant by detector described in the geometrical model circulating analog for covering card building and waits for
After surveying radioactive source, the measurement data simulated when gamma events obtained by the detector switch to the point of impact every time is obtained respectively, and will
The analogue measurement data got enter in the preset mode respectively as current continuous data every time calculates, and obtains every
Same specified nucleic, is further modeled by a kind of analog probability weighted value of specified nucleic when it is modeled every time every time
Obtained analog probability weighted value is that column vector forms its corresponding homotype matrix；Wherein, the actual measurement measurement data and described
Analogue measurement data include three-dimensional position, hit time and the energy deposition of the point of impact；
Detailed process is, unlike the gamma spectrometer of the common nucleic activity that converted using full energy peak counting, certain
The corresponding virtual circular conical surface of the Compton scatter imaging of a space lattice can all contribute other grids in space, as n member to
Each of amount b element is from the superposition of the contribution of all n source item grids, it is therefore desirable to which the matrix of n × n could be anti-
The correlation for reflecting n source item activity element and n probability space element remembers that the matrix of this n × n is efficiency calibration matrix.Effect
The jth of rate scale matrix shows n element, successively represents when only j-th of source item grid is there are when unit activity nucleic, right
Contribution of all n source item grids in probability space matrix.Therefore detection efficiency calibration is sought to efficiency calibration matrix
All elements are decided.
Therefore, it is necessary to establish space locating for radioactive source to be measured and the detector in the nuclear power plant using covering card program
Geometrical model, and with each specify the classification of nucleic by mock up flat and its correspond to be made of actual measurement probability right value it is single-row
The element number of vector is recurring number, after detecting nuclear power plant's radioactive source to be measured by geometrical model circulating analog detector, respectively
Obtain measurement data when gamma events obtained by each analog prober switch to the point of impact, and the analogue measurement that will be got every time
Data enter in preset mode respectively as current continuous data to be calculated, and obtains each specified nucleic when it is modeled every time
Analog probability weighted value, the analog probability weighted value for being further modeled same specified nucleic every time be column vector
Form its corresponding homotype matrix.
It is understood that during geometrical model circulating analog each can be confined according in step S1 in fact
The cube network in specified nucleic corresponding three-dimensional space, only needs circulating analog detector to the spatial cuboids grid confined in this way
Detection efficient, obtain analog probability weighted value that each specified nucleic recycles each time, will further follow each time
The form for the analog probability weighted value defiled vector that ring obtains, and all after circulation terminates by each of same specified nucleic
A single-row vector lines up homotype matrix.
It can be seen that every completion one cycle, the efficiency calibration matrix of specified nucleic just fills in a column, until recycling above
It is fully completed, the efficiency calibration matrix of entire n × n is just filled, that is, forms homotype matrix A.
In embodiments of the present invention, in the cyclic process each time of detection efficiency calibration, the analogue measurement number of nucleic is specified
It is calculated according to continuous data can be taken as to enter preset mode, surveys measurement data in the process and step S1 of each cycle calculations
The process for entering preset mode calculating as current continuous data is identical, and the result only finally obtained is different, that is, works as inspection
Measure current continuous data be analogue measurement data when, using the product of the screened cube grid of each of imparting as currently
The analog probability weighted value of specified nucleic, specific calculating process refer to step S11 to step S14, and this is no longer going to repeat them.
Step S3, each obtained according to specifies nucleic to be corresponded to as it single-row composed by actual measurement probability right value
Vector and by its correspond to analog probability weighted value be column vector be formed by homotype matrix, by equation Ax=b, calculate each
The activity distribution of the specified nucleic of kind；Wherein, A is that correspond to analog probability weighted value by it be column vector institute shape to each specified nucleic
At homotype matrix, b is that each specified nucleic as it corresponds to single-row vector composed by actual measurement probability right value, and x is each
The vector that be solved activity value of the specified nucleic of kind in each space lattice confined is lined up.
Detailed process is to determine detection efficient matrix, i.e., after homotype matrix A, it is known that probability space vector b with not
The relationship between source item activity vector x known, i.e., available matrix and vector multiplication are concisely expressed as equation Ax=b.It is neat to solve this
Sublinear equation group finds out vector x to get the nucleic activity of n source item grid has been arrived.
The application scenarios for the method that the distribution of nuclear power plant's nucleic activity is measured in the embodiment of the present invention are described further, with
In workshop of the tool there are three horizontal pipe, contain in measurement horizontal pipe58For Co nucleic activity, it is described as follows:
Before computer disposal, a cadmium-zinc-teiluride semiconductor array with the sensitive read out function of three-dimensional position is selected to visit
Device is surveyed, number of pixels is 11 × 11, and detector is placed in front of horizontal pipe on ground, is with horizontal pipe minimum distance
4m, booting detection 10min, record actual measurement measurement data, i.e., three-dimensional position, hit time and the energy of each point of impact sink
Product passes through total data on network cable transmission to computer after to be detected；
After computer gets data, " double point of impact events " screening is carried out in actual measurement measurement data, leaves 68433
" double point of impact events ", determines nucleic58The characteristic gamma ray of Co is 810.8keV, according to the sensitive gamma detector of three-dimensional position
Energy resolution R=2%, converse nucleic58Energy window range of the Co in power spectrum is 790.2keV-831.4keV；
Summation is deposited to the energy of two points of impact in each group " double point of impact events " (retaining combination), judges energy
Whether the sum of deposition belongs within the scope of the energy window of 790.2keV-831.4keV；If belonging to, continue to retain, and be included into core
Element58In the combination of Co；If being not belonging to, give up；
To nucleic58Any combination of Co, because of gamma energy E=810.8keV > 400keV, therefore by nucleic58Co is all
Energy deposits the biggish point of impact and is labeled as Compton scattering point in two points of impact in combination, and energy deposits lesser hit
Point is labeled as photoelectric absorption point；
To nucleic58Each combination of Co be unit, with from photoelectric absorption point to the vector of Compton scattering point be reference side
To, and remember nucleic58The energy of Compton scattering point is deposited as E in each combination of Co1, converse nucleic58Health in each combination of Co
General scatteringangleθ；At this point, using the coordinate of Compton scattering point in space as vertex, using reference direction as axis, using θ as half cone
Angle constitutes virtual circular conical surface in space, then it is each combination correspond to one as virtual circular conical surface；
Establish three-dimensional cartesian coordinate system in a computer for the workshop of three horizontal pipes, workshop having a size of 5m × 5m × 5m,
And cube grid is divided, size of mesh opening is set as 4cm, stores a probability right in a computer for each cube grid
Variable, initial value are 0；
To all virtual circular conical surfaces, carry out discretization traversal according to double round-robin method below one by one: first follows again
Ring: using bus length as amplitude variations, it is incremented by traversal from 0 to 650cm, amplitude delta is set as 1cm；Second recirculates: for
First recirculates with the perimeter of the corresponding circle of bus length, and with the central angle of the circleFor angle variables, incremental time of π from 0 to 2
It goes through, angle step is set asAbove-mentioned double each point looped through first judges which it belongs to according to its coordinate
One space lattice, then add up a upper value for the corresponding probability right of the grid, this value is set as
Complete nucleic58After the traversal of all virtual circular conical surfaces of Co, nucleic is obtained58The actual measurement probability right value of Co, to need
Further progress detection efficiency calibration；
At this point, space lattice is compareed with the 3-D geometric model of workshop, there may be source item nucleic in workshop
Component is three horizontal pipes, and the grid that they are accommodated shares 360, these grids are known as source item grid, remembers its number n=
360, then each source item grid Radionuclide58The activity of Co is all unknown number to be solved.It is source item according to sequence from high to low
Grid is successively numbered with 1 to 360 serial number, will be denoted as activity unknown number vector x, it has 360 elements.At the same time, it obtains
Probability space array in sequentially number filter out the corresponding actual measurement probability right value of source item grid, they are formed a line be denoted as to
B is measured, it also there are 360 elements；
Remember that efficiency calibration matrix (i.e. homotype matrix) is A, it is 360 × 360 square matrix, and defeated by the particle of computer
Monte Carlo simulation program is transported to carry out: establishing 360 × 360 array with storage matrix A；Factory is established with card program Geant4 is covered
Room, three horizontal pipes, in pipe water, detector geometrical model, only setting unit is living in j-th of source item grid for covering card mold type
The nucleic of degree generates gamma ray according to emission probability, then carries out all events for covering card analog prober record, newly-built
Probability space carries out probability cone traversal, the probability right of all source item grids in probability space is read according to number, and write according to number
Enter the 1st to the 360th element of matrix A jth column.After the completion of the above circulation, entire efficiency calibration matrix A is just filled.
System of homogeneous linear equations Ax=b is solved, finds out vector x to get to 360 source item grids58Co nucleic activity, from
And the nucleic in three horizontal pipes58The activity distribution of Co is with regard to this determination.
The implementation of the embodiments of the present invention has the following beneficial effects:
1, in embodiments of the present invention, resulting actual measurement measures number either after detector direct detection radioactive source to be measured
According to or analog prober detect resulting analogue measurement data after radioactive source to be measured, the two includes that the point of impact (radiates
" hot spot ", nucleic) three-dimensional position (x × y × z), energy deposition (i), and the two be involved in preset mode calculate come
Activity (j) distribution situation of nucleic out, thus set up nuclear power plant radiation " hot spot " simultaneously with three-dimensional position, energy and intensity phase
It closes (giving x × y × z × i × j matrix of three big key parameters), overcomes existing radiation " hot spot " detection means not
Foot；
2, analogue measurement data obtained by after in embodiments of the present invention, detecting radioactive source to be measured as analog prober are corresponding
Analog probability weighted value be formed by homotype matrix to correct resulting actual measurement after detector direct detection radioactive source to be measured and survey
The actual measurement probability right value of amount data is formed by single-row vector, and the activity distribution situation of the nucleic obtained is more accurate, to mention
High computational accuracy.
Those of ordinary skill in the art will appreciate that implement the method for the above embodiments be can be with
Relevant hardware is instructed to complete by program, the program can be stored in a computer readable storage medium,
The storage medium, such as ROM/RAM, disk, CD.
The above disclosure is only the preferred embodiments of the present invention, cannot limit the right model of the present invention with this certainly
It encloses, therefore equivalent changes made in accordance with the claims of the present invention, is still within the scope of the present invention.
Claims (9)
1. a kind of method of measurement nuclear power plant's nucleic activity distribution, which is characterized in that the described method includes:
Obtain specifies nucleic and gained to correspond to and switch to hit inside gamma events after surveying nuclear power plant's radioactive source to be measured by detector
The measurement data of point, and enter in preset mode using the actual measurement measurement data got as current continuous data and calculate,
And specify the classification of nucleic as unit of account using each, the actual measurement probability right value of each specified nucleic is respectively obtained, into
One step obtains each specified nucleic and corresponds to single-row vector composed by actual measurement probability right value as it and correspond to single-row vector
Element number；
Using the geometrical model for covering card program and establishing space and the detector locating for radioactive source to be measured in the nuclear power plant, and with
The classification of each specified nucleic is made of the element of single-row vector mock up flat and its correspondence actual measurement probability right value
Number is recurring number, detects nuclear power plant's radioactive source to be measured by detector described in the geometrical model circulating analog for covering card building
Afterwards, the measurement data simulated when gamma events obtained by the detector switch to the point of impact every time is obtained respectively, and will be described every time
The analogue measurement data got enter in the preset mode respectively as current continuous data to be calculated, and it is specified to obtain each
Analog probability weighted value of the nucleic when it is modeled every time, the mould for being further modeled same specified nucleic every time
Quasi-probability weighted value is that column vector forms its corresponding homotype matrix；Wherein, the actual measurement measurement data and the analogue measurement
Data include three-dimensional position, hit time and the energy deposition of the point of impact；
It specifies nucleic to be corresponded to as it according to each obtained and surveys single-row vector composed by probability right value and by it
Corresponding analog probability weighted value is that column vector is formed by homotype matrix, by equation Ax=b, calculates each specified nucleic
Activity distribution；Wherein, A is that correspond to analog probability weighted value by it be that column vector is formed by homotype square to each specified nucleic
Battle array, b are each specified nucleic single-row vector as composed by its correspondence actual measurement probability right value, and x is each specified nucleic
The vector that activity value to be solved in each space lattice confined is lined up；
Wherein, the current continuous data enters the specific steps that calculate in the preset mode and includes:
Determine the classification of corresponding currently assigned nucleic when current continuous data enters calculating, and according to the class of currently assigned nucleic
Not, in preset nucleic characteristic gamma ray energy scale, the gamma energy of currently assigned nucleic is obtained, and according to described
The gamma energy of the preset energy resolution ratio of detector and the currently assigned nucleic determines currently assigned nucleic in energy
Energy window range in spectrum；
According to the hit time of each point of impact in current continuous data, hits all in the current continuous data are clicked through
Row primary screening obtains the point of impact for meeting default combination condition and its combination of the corresponding point of impact, and according to the current finger
Determine each point of impact in the gamma energy and its corresponding energy window range and the current continuous data of nucleic
Energy deposition carries out postsearch screening, the point of impact needed for obtaining currently assigned nucleic to the point of impact that primary screening obtains respectively
And its corresponding point of impact combination, and further according to the gamma energy of the currently assigned nucleic and its corresponding hit
Point combination, obtains the Compton scattering point and photoelectric absorption point of currently assigned nucleic；
It is deposited according to the three-dimensional position of each point of impact in current continuous data and energy, determines in currently assigned nucleic and own
The three-dimensional position and energy of Compton scattering point and photoelectric absorption point deposition in point of impact combination, and in currently assigned nucleic
The combination of any group of point of impact is unit, according to Compton scattering point and photoelectricity in each group of point of impact combination in currently assigned nucleic
The three-dimensional position of point and the gamma energy of energy deposition and currently assigned nucleic are absorbed, to any in currently assigned nucleic
Point of impact combination progress circular conical surface is virtual, obtains combining corresponding virtual circular cone with the point of impact each in currently assigned nucleic
Face；Wherein, each described virtual circular conical surface is to correspond to Compton scattering point in point of impact combination in currently assigned nucleic
Three-dimensional position be vertex, with correspond in currently assigned nucleic the point of impact combine in Compton scattering point to opposite photoelectric absorption point
Vector be axis and specific Compton scattering angle is corresponded in point of impact combination using in currently assigned nucleic as semi-cone angle building and
At；Specific Compton scattering angle is to correspond to point of impact group in currently assigned nucleic by it in each described virtual circular conical surface
The energy deposition of Compton scattering point and the gamma energy of currently assigned nucleic determine in conjunction；
Discretization traversal processing is carried out each described virtual circular conical surface obtained in currently assigned nucleic, and according to discrete
Change traversal processing as a result, in the cube grid that preset three-dimensional space is divided, filtering out storage has currently assigned nucleic
The cube grid of interior virtual circular conical surface and its corresponding quantity for storing virtual circular conical surface, and further screened according to each
Cube grid stores the quantity of virtual circular conical surface, and obtaining currently assigned nucleic corresponding to current continuous data is actual measurement survey
Measure data when actual measurement probability right value or currently assigned nucleic correspond to current continuous data be the analogue measurement data when
Analog probability weighted value；Wherein, the preset three-dimensional space is by locating for radioactive source to be measured in the building nuclear power plant
The three-dimensional cartesian coordinate system that space matches is realized, including multiple cube grids with identical specifiable lattice size.
2. the method as described in claim 1, which is characterized in that the life of each point of impact in the current continuous data of basis
The middle time carries out primary screening to the points of impact all in the current continuous data, obtains the hit for meeting default combination condition
Point and its corresponding point of impact combination, and according to the gamma energy of the currently assigned nucleic and its corresponding energy window model
Enclose and the current continuous data in each point of impact energy deposition, the point of impact obtained respectively to primary screening carries out
Postsearch screening, the point of impact needed for obtaining currently assigned nucleic and its combination of the corresponding point of impact, and further work as according to
The gamma energy of preceding specified nucleic and its corresponding point of impact combination, obtain currently assigned nucleic Compton scattering point and
The step of photoelectric absorption point, specifically includes:
It is ordered to any combination of two of the point of impact in the current continuous data, and according to each in the current continuous data
The hit time at midpoint screens two points of impact of all any combination, retains and meet the default combobar out
The point of impact of part and its combination of formation；
According to the energy deposition of each point of impact in the current continuous data, determine that the energy for retaining the point of impact is heavy
Product, and the energy deposition that calculates every group of point of impact in the corresponding combination of the reservation point of impact is the sum of cumulative；
According to the energy window range of the currently assigned nucleic and it is calculated retain combine in every group of point of impact energy
Deposition is the sum of cumulative, screens to reservations combination, obtains currently assigned nucleic and meet the group that preset energy compares condition
Close and its correspond to the required point of impact；
According to the gamma energy of the currently assigned nucleic and its corresponding combination, it is set in the gamma of currently assigned nucleic
When ray energy is greater than or equal to preset threshold, it is equal to deposit the big point of impact for energy in the corresponding any combination of currently assigned nucleic
Depositing the small point of impact for Compton scattering point, energy is photoelectric absorption point；Or it is set in the gamma of currently assigned nucleic and penetrates
It is light that energy, which deposits the big point of impact, when heat input is less than the preset threshold, in the corresponding any combination of currently assigned nucleic
It is Compton scattering point that electric absorption point, energy, which deposit the small point of impact,.
3. method according to claim 2, which is characterized in that the default combination condition is two among any reservation combination
The hit time interval of the point of impact should be less than the detector response time, and two points of impact have among any reservation combination
There is uniqueness.
4. method according to claim 2, which is characterized in that the preset energy comparison condition is two in any reservation combination
The energy deposition of a point of impact is the sum of cumulative to be located within the scope of the energy window of the currently assigned nucleic.
5. the method as described in claim 1, which is characterized in that specific Compton in each described described virtual circular conical surface
Angle of scattering passes through formulaTo realize；Wherein, θ is Compton scattering angle, E1It is current
The energy of Compton scattering point deposits in any point of impact combination in specified nucleic, E0For the gamma ray energy of currently assigned nucleic
Amount, mec2It is constant for photon quality.
6. the method as described in claim 1, which is characterized in that described obtained described in each in currently assigned nucleic
Virtual circular conical surface carries out discretization traversal processing, and according to discretization traversal processing as a result, being divided in preset three-dimensional space
Cube grid in, filtering out storage has in currently assigned nucleic the cube grid of virtual circular conical surface and its corresponding storage void
The quantity of quasi- circular conical surface, and the quantity of virtual circular conical surface is further stored according to each screened cube grid, worked as
Preceding specified nucleic corresponds to actual measurement probability right value or currently assigned core when current continuous data is the actual measurement measurement data
The step of plain analog probability weighted value corresponded to when current continuous data is the analogue measurement data, specifically includes:
All cube grids in the preset three-dimensional space are assigned a value of 0；
First is executed each described virtual circular conical surface obtained in currently assigned nucleic to recirculate after traversal, is continued to working as
Each obtained described virtual circular conical surface executes second and recirculates traversal in preceding specified nucleic, filters out double searching loop
Storage has the cube grid of virtual circular conical surface in currently assigned nucleic and counts quilt in each screened cube grid afterwards
The traversed quantity of virtual circular conical surface；Wherein, described first recirculate traversal using imaginary circles cone element length as amplitude variations,
And set amplitude variations value and carry out being incremented by traversal with specific amplitude increment since 0, until set amplitude variations value exceeds
Until the boundary of the preset three-dimensional space；Described second recirculates traversal when being respectively radius of circle with each amplitude variations value
Corresponding central angle is angle variables, and set angle variate-value carries out being incremented by traversal with special angle increment since 0, directly
Until set angle variables value is 2 π；Wherein, the specific amplitude increment is set as cube grid specifiable lattice size
1/10-1/3 one；It is corresponding in cube grid specifiable lattice size 1/10-1/5 that the special angle increment is set as arc length
Its central angle for the moment；
By each screened cube grid by the traversed quantity of virtual circular conical surface simultaneously multiplied by a given value, and will
Obtained product, which respectively corresponds, assigns each screened cube grid；
When detecting current continuous data is the actual measurement measurement data, by each screened cube net of the imparting
Actual measurement probability right value of the product of lattice as currently assigned nucleic；
When detecting current continuous data is the analogue measurement data, by each screened cube net of the imparting
Analog probability weighted value of the product of lattice as currently assigned nucleic.
7. such as method of any of claims 1-6, which is characterized in that the actual measurement measurement data and the simulation are surveyed
The three-dimensional position X of the point of impact, Y-direction are determined by the pixel serial number of the detector in amount, and Z-direction is to utilize core
The electronics of electronics record gamma events drifts about duration to determine.
8. such as method of any of claims 1-6, which is characterized in that the actual measurement measurement data be by will described in
Detector is placed in outside space locating for radioactive source to be measured described in nuclear power plant and apart from 1 to 10 meter of radioactive source of the range to be measured
It is interior, it opens and detects the radioactive source to be measured 1 to 120 minute and obtain.
9. such as method of any of claims 1-6, which is characterized in that the classification of the specified nucleic includes58Co、60Co、110mAg、124Sb、137Cs、51Cr、54Mn、59Fe、95Zr、95Nb、134Cs、131I。
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710216323.8A CN107195342B (en) | 2017-04-05 | 2017-04-05 | A method of measurement nuclear power plant's nucleic activity distribution |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710216323.8A CN107195342B (en) | 2017-04-05 | 2017-04-05 | A method of measurement nuclear power plant's nucleic activity distribution |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN107195342A CN107195342A (en) | 2017-09-22 |
| CN107195342B true CN107195342B (en) | 2019-07-30 |
Family
ID=59871088
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201710216323.8A Active CN107195342B (en) | 2017-04-05 | 2017-04-05 | A method of measurement nuclear power plant's nucleic activity distribution |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN107195342B (en) |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108319160B (en) * | 2018-02-01 | 2021-04-16 | 中国核电工程有限公司 | Nuclear power station main control room simulator system based on virtual reality technology |
| CN108535768B (en) * | 2018-03-13 | 2021-08-20 | 江苏超敏科技有限公司 | Gamma camera based on double-detector technology |
| CN109814147B (en) * | 2019-01-01 | 2021-01-29 | 中国人民解放军63653部队 | Method for measuring gamma radionuclide distribution around small hole by using detector and attenuator |
| CN111175803B (en) * | 2020-01-12 | 2021-01-12 | 兰州大学 | Borehole core facility retired waste radioactive multi-parameter detection system and method |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103853929A (en) * | 2014-03-17 | 2014-06-11 | 东华理工大学 | Low-resolution gamma energy spectrum inversion analysis process and method based on Monte Carlo response matrix |
| CN104020507A (en) * | 2014-06-13 | 2014-09-03 | 西北核技术研究所 | Radioactivity area determining method based on virtual point detector principle |
| CN204009085U (en) * | 2014-07-15 | 2014-12-10 | 中广核工程有限公司 | A kind of nuclear power plant hydrogeneous waste gas radioactivity continuous monitoring device |
| CN105355256A (en) * | 2015-09-30 | 2016-02-24 | 湖北省农业科学院农产品加工与核农技术研究所 | Method for arranging radioactive sources |
| CN106199676A (en) * | 2015-04-30 | 2016-12-07 | 北京中智核安科技有限公司 | A kind of gamma detector passive efficiency scale new method |
-
2017
- 2017-04-05 CN CN201710216323.8A patent/CN107195342B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103853929A (en) * | 2014-03-17 | 2014-06-11 | 东华理工大学 | Low-resolution gamma energy spectrum inversion analysis process and method based on Monte Carlo response matrix |
| CN104020507A (en) * | 2014-06-13 | 2014-09-03 | 西北核技术研究所 | Radioactivity area determining method based on virtual point detector principle |
| CN204009085U (en) * | 2014-07-15 | 2014-12-10 | 中广核工程有限公司 | A kind of nuclear power plant hydrogeneous waste gas radioactivity continuous monitoring device |
| CN106199676A (en) * | 2015-04-30 | 2016-12-07 | 北京中智核安科技有限公司 | A kind of gamma detector passive efficiency scale new method |
| CN105355256A (en) * | 2015-09-30 | 2016-02-24 | 湖北省农业科学院农产品加工与核农技术研究所 | Method for arranging radioactive sources |
Also Published As
| Publication number | Publication date |
|---|---|
| CN107195342A (en) | 2017-09-22 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN107195342B (en) | A method of measurement nuclear power plant's nucleic activity distribution | |
| Hassanein | Correction methods for the quantitative evaluation of thermal neutron tomography | |
| US9958561B2 (en) | Apparatus and method for the determination of one or more neutron source characteristics | |
| CN103645491B (en) | Radioactive source localization method, Apparatus and system | |
| US7279676B2 (en) | Position sensitive radiation spectrometer | |
| CN103901052B (en) | A kind of SGS and TGS combined measurement device and collimating apparatus optimization method | |
| Polf et al. | Applications of machine learning to improve the clinical viability of Compton camera based in vivo range verification in proton radiotherapy | |
| CN107688194A (en) | Data processing method and data processing equipment | |
| CN109239757B (en) | Device and method for measuring and diagnosing distribution of intense pulse gamma radiation dose field | |
| Lintereur et al. | Boron-10 lined proportional counter model validation | |
| Poitrasson-Rivière et al. | Monte Carlo investigation of a high-efficiency, two-plane Compton camera for long-range localization of radioactive materials | |
| Lévai et al. | Feasibility of gamma emission tomography for partial defect verification of spent LWR fuel assemblies: Summary report on simulation and experimental studies including design options and cost-benefit analysis: Task JNT A1201 of the Support Programmes of Finland (FINSP), Hungary (HUNSP) and Sweden (SWESP) to the IAEA Safeguards | |
| Olson et al. | Passive detection of small low-emission sources: two-dimensional numerical case studies | |
| Kähkönen | Evaluating the viability of Serpent in Passive Gamma Emission Tomography (PGET) radiation transport simulations | |
| CN106991511B (en) | Strong backward thrust method and system for point source, line source and surface source combined composite radiation source of nuclear power plant | |
| US7564041B2 (en) | Method of using self-positioning radiation counters | |
| Schulz et al. | Quantitative assessment of scanning-system parameters | |
| Virta et al. | Verifying spent nuclear fuel with Passive Gamma Emission Tomography prior to disposal in a geological repository in Finland | |
| JP6814049B2 (en) | Subcriticality measurement method for nuclear fuel | |
| Stockman et al. | Facility scale in-situ source localization and assay via a sparse 3He neutron detector array: enhancing nuclear material control and accounting in nuclear fuel cycle facilities | |
| Checchia et al. | Muon tomography for spent nuclear fuel control | |
| Gagliardi et al. | Novel applications of state-of-the-art gamma-ray imaging technique: from nuclear decommissioning and radioprotection to radiological characterization and safeguards | |
| Georgadze | Optimization Study of a Muon Tomography System for Imaging of Nuclear Waste Containers. | |
| Brown et al. | Thermal neutron source location using a 3-D position-sensitive CdZnTe detector array | |
| Montz | Uranium Holdup Mass Quantification by Hybrid Gamma Imaging |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |