CN104714245A - Semi-chromatography gamma scanning method for low-medium radioactive waste barrel measurement - Google Patents

Semi-chromatography gamma scanning method for low-medium radioactive waste barrel measurement Download PDF

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CN104714245A
CN104714245A CN201510067662.5A CN201510067662A CN104714245A CN 104714245 A CN104714245 A CN 104714245A CN 201510067662 A CN201510067662 A CN 201510067662A CN 104714245 A CN104714245 A CN 104714245A
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detector
layer
pail
used dressings
section
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CN104714245B (en
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王德忠
顾卫国
钱楠
马云巍
尹俊连
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Shanghai Jiaotong University
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Shanghai Jiaotong University
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Abstract

The invention provides a semi-chromatography gamma scanning method for low-medium radioactive waste barrel measurement. A rotary platform, a detector platform, a detector with a collimator, a transmission source platform, a transmission source, a shielding part of the transmission source and an analysis module are adopted in the method. A waste barrel is divided into multiple section layers in the height direction, the waste barrel is rotated, surface distribution of radioactive point sources on the section layers is changed into linear distribution of ring sources in the radius direction, the detector conducts measurement at different section layer heights and different eccentric positions in the section layers, an equation set reflecting the mutual relation between the detector counting rate and the activity of nuclide in annular grids is established, the equation set is solved, distribution of the activity of the radioactive nuclide in the waste barrel in the diameter direction and the height direction of the barrel is acquired, and the total activity of the radioactive nuclide in the waste barrel is acquired through summation. The method is high in measurement accuracy, short in measurement time and high in practical value and application prospect.

Description

The half tomographic gamma scan method that middle cold waste bucket is measured
Technical field
What the present invention relates to is a kind of gamma scan method and activity reconstruction technique of carrying out nucleic and activity measurement for low-activity barreled refuse in nuclear power plant, and based on the related device of this technology, specifically utilize radiation detector to measure the gamma rays at the uniform velocity rotating in pail for used dressings and send, then reconstruct radioactive nuclide and activity scanning technique with axial distribution radial along pail for used dressings thereof.
Background technology
Along with country greatly develops nuclear power, a large amount of middle cold waste produced during nuclear power runs urgently is disposed.According to the regulation such as standard GB/T 11928-1989, GB9132-1988, these refuses are carried out that centre is temporary, transport, surface contamination must be carried out before final disposal and dose rate detects, nuclide identification and activity measurement in bucket.Because measuring object is for containing active large volume barreled refuse, therefore Measurement accuracy is carried out to nucleic in bucket and activity and there is certain difficulty.At present, desirably Dynamic Non-Destruction Measurement, γ scanning technology is one of most popular nuclear power plant barreled refuse detection method, comprise segmentation gamma scanning technique (Segmented Gamma Sacnning, and tomographic gamma scanning technique (Tomographic Gamma Sacnning, TGS) SGS).Its principle is, measures the amplitude of gamma rays and counting by radiation detector, then the power spectrum of the gamma rays recorded by MCA analysis, thus determines that nucleic kind and corresponding nucleic send feature gamma ray count rate.Because nucleic exists distribution in bucket, and the ray sent also is subject to the attenuation by absorption of material in bucket, therefore needs to set up the relation of each nucleic activity in meter digit rate and bucket.Pail for used dressings is divided into some layers along short transverse by the SGS that nineteen seventies grows up, suppose that in tomography, material and nucleic are uniformly distributed, the relation of meter digit rate and activity is set up with this, and define the scan mode of this detection method, namely pail for used dressings at the uniform velocity rotates (object reduces the unevenness of radioactive nuclide circumferencial direction distribution in bucket), just the lifting of each tomography successively stepping is measured with radiation detector, the distribution of radioactivity along pail for used dressings axis can be obtained by the method.SGS is owing to thinking that radioactive nuclide is uniformly distributed in pail for used dressings, and the activity after reconstruction is very large with actual value phase ratio error.The TGS that nineteen nineties proposes, on the basis of SGS technology, introduces computed tomography scanning technology to the measurement of each section of layer, can calculate, obtaining the distributed in three dimensions of bucket inner stuffing matter and radionuclide specific activity, substantially increasing measuring accuracy by rebuilding.The method needs to carry out computed tomography scanning, namely detector is measured from each different directions and position pail for used dressings, as pail for used dressings stepping is rotated, detector eccentric center translation in the horizontal plane and the lifting along short transverse, although therefore TGS measuring accuracy is high, but, the time complicated to measuring process is tens times of SGS, limits its widespread use.
, low precision short for SGS Measuring Time, the feature that TGS measuring accuracy is high, the time is long, seeking the Detection Techniques that Measuring Time is relatively short, measuring accuracy is relatively high will have important value and application prospect.For this reason, a kind of modified SGS technology based on double detector (Improved Segmented Gamma Sacnning, ISGS) be suggested, its principle is on the basis of SGS, and the radioactive nuclide in each section of layer is equivalent to Single Point Source by its distribution, because when measuring, pail for used dressings at the uniform velocity rotates, this point source is linear loop source, by the radius in two probe position determination ring sources, to the location in source, detection efficiency can accurately be calculated, therefore detection accuracy comparatively SGS greatly improve.The method has very high detection accuracy to the situation that point source exists, but precision can reduce when multiple sources.
Summary of the invention
The present invention is directed to above-mentioned the deficiencies in the prior art, half chromatography (the Semi-Tomography Gamma Scanning that a kind of middle cold waste bucket is measured is proposed, STGS) gamma scanning scan method, the half tomographic gamma scanning between SGS and TGS that the present invention proposes, radioactive nuclide (ring-type existence) distribution on section layer radius and pail for used dressings short transverse when can obtain pail for used dressings wheel measuring, measuring accuracy higher than SGS, and enormously simplify measuring process, shortens Measuring Time compared with TGS.
For achieving the above object, the technical solution adopted in the present invention is as follows:
The half tomographic gamma scan method that a kind of middle cold waste bucket is measured, the scanister that the method adopts comprises universal stage, detector platform, there is the detector of collimating apparatus, transmission source platform, transmission source and shield member thereof, analysis module, described radioactive waste bucket at the uniform velocity rotates when scanning survey, in bucket, radioactive nuclide relative bucket external detector after rotating is equivalent to annular line source by point source, pail for used dressings is divided some sections of layers vertically, each section of layer inner stuffing matter is uniformly distributed, some ring-type grids are divided again by each section of layer, measured by some eccentric positions of detector in each section of layer, in each ring-type grid of reconstruction calculating acquisition, radionuclide specific activity is along the radial and axial distribution of pail for used dressings, realize quick to the radioactivity of pail for used dressings, measure accurately.
Specifically comprise the following steps:
The first step, adjustment detector and the particular location of collimating apparatus, transmission source and shield member thereof thereof, make detector axis aim at pail for used dressings center and by transmission source collimating aperture;
Second step, carry out the scanning of current layer
Pail for used dressings at the uniform velocity rotates with certain rotating speed, gathers gamma-spectrometric data; Make pail for used dressings center be followed successively by predetermined distance to the distance of detector axis, altogether gather several gamma-spectrometric datas of this section of layer;
3rd step, by detector platform and transmission source platform from the pail for used dressings bottom, move transmission source platform and detector platform in the vertical direction simultaneously, successively scan, every layer of scanning all repeats second step;
4th step, data processing
First the transmission measurement of each section of layer is carried out, obtain this section of layer material to the mean attenuation coefficient of ray, secondly each section of layer is divided the ring-type grid of homalographic along radial direction, calculate the detection efficiency through material correction for attenuation of each grid to detector, the system of equations of Detector count rate mutual relationship when setting up each ring-type grid radionuclide specific activity of reflection and be in each detecting location, solving equation group obtains radionuclide specific activity distribution along direction, bucket footpath and short transverse in pail for used dressings, and summation obtains the total activity of radioactive nuclide in pail for used dressings.
In described second step, pail for used dressings at the uniform velocity rotates with certain rotating speed, and a concrete Measuring Time measuring position being gathered to its gamma-spectrometric data is determined with radioactive level.
The data processing of described 4th step comprises transmission reconstruction and launches rebuilds, wherein transmission reconstruction is the computational analysis carried out the attenuation coefficient of ray or density to obtain pail for used dressings each section of layer filler, and launching reconstruction is the computational analysis carried out to obtain radionuclide specific activity distribution in pail for used dressings.
The concrete grammar of described transmission reconstruction is:
Think that material is uniformly distributed in each layer, if P iequal the transmissivity that detector records when i-th section layer position eccentric position is zero: P i=C i/ C max, wherein: i=1,2 ..., I, C ithe gamma photons full energy peak counting rate that when indicating that pail for used dressings exists, detector records i-th section layer position; C maxthe γ photon full energy peak counting rate that when representing that the gamma-rays that transmission source sends is not decayed by sample, detector records, the pass of transmissivity and attenuation coefficient is: μ id=-ln (P i), wherein μ ibe that in i-th section layer, material is to the attenuation coefficient of ray, D is pail for used dressings diameter.
The described concrete grammar rebuild of launching is:
Decay owing to all will produce with matter interaction in bucket before the ray arrival detector that radioactive nuclide in bucket sends, therefore correction for attenuation must be carried out, when detector is just to i-th section layer jth eccentric position, in m layer n-th ring-type grid, radioactive nuclide sends ray and is detected the counting rate that device records and is: C mn, ij=α ε mn, ijχ mn, ija mn, wherein α is the branching ratio of considered ray energy, ε mn, ijbe in m layer n-th ring-type grid radioactive nuclide to the detection efficiency of detector when being in i-th section layer jth eccentric position; A mnit is radionuclide specific activity in m layer n-th ring-type grid; Attenuation correction coefficient χ mn, ij=exp (-Σ ul), μ and l each layer attenuation coefficient that to be m layer n-th ring-type grid experience to detector and average track lenth, consider that detector can record the ray that in whole pail for used dressings, all grids send, the counting rate that detector when being in i-th section layer jth eccentric position records is: in conjunction with the detection of all positions, composition unknown number number is I × N, and equation number is the system of linear equations of I × J:
Wherein, P=I × J, Q=I × N, e=α ε χ, I, J are integer, solve this system of linear equations, and obtain the distribution along direction, bucket footpath and short transverse in pail for used dressings of the activity of radioactive nuclide, summation obtains the total activity of whole pail for used dressings A = Σ 1 ≤ q ≤ Q A q .
Pail for used dressings segments I is 9, and eccentric position number J span is 2 to 8, and the ring-type grid number N of each section of layer is not more than J.
The ring-type grid number N of each section of layer is identical with eccentric position number J.
The positional number of described measurement and equation number, be no less than the grid number that namely unknown number number divides, i.e. P >=Q.
The method solving this system of linear equations is the alternative manner based on probability statistics.
Compared with traditional γ scanning technology, the present invention has the following advantages:
(1) compared with SGS, STGS can obtain the distribution of nucleic in section layer, and therefore measuring accuracy improves greatly, and Measuring Time only increases several times (concrete relevant with number of grid).In actual measurement, STGS and SGS all requires that pail for used dressings at the uniform velocity rotates, and detector is along pail for used dressings short transverse stepping lifting (as 9 times), but STGS also needs in each section of layer plane, carry out several times eccentric center translation (as 4 times or 8 times), realizes computed tomography scanning.
(2) compared with TGS, STGS is rotated by pail for used dressings, section layer inner face (two dimension) distribution is reduced to radial direction (one dimension) distribution, simplify scanning process, Measuring Time can shorten an order of magnitude, and be all the application of chromatographic technique, measuring accuracy does not obviously reduce.In actual measurement, TGS requires that pail for used dressings carries out stepping rotation (as 24 times), detector stepping eccentric center translation (as 4 times) and stepping lifting (as 9 times), STGS requires that pail for used dressings at the uniform velocity rotates, because this reducing the process of pail for used dressings being carried out to circumference stepping measurement.
(3) compared with ISGS, STGS rebuilds according to ring source distribution feature, and do not adopt as ISGS point source hypothesis arranges assumed conditions to measuring technique, therefore measuring technique is more reasonable, and more applicable multiple sources and even nucleic are uniformly distributed the measurement of situation.In actual measurement, STGS and ISGS all requires pail for used dressings at the uniform velocity to rotate and detector stepping lifting, but ISGS only needs in section layer plane bias mobile once, and STGS needs bias mobile repeatedly (as 4 times or 8 times), and Measuring Time is longer.
Current national standard only requires to measure the kind of nucleic in pail for used dressings and total activity, does not require that obtaining it specifically distributes.Utilize gamma scanning technique to carry out nucleic and activity measurement to radioactive waste bucket, the same radioactive level of its precision, nucleic are all relevant with filler homogeneity, detector etc.For middle low-activity barreled refuse, the nucleic that radioactive level is higher exists with focus form, Radio-nuclide distribution lack of homogeneity; Meanwhile, the compressed barrelling of filler, Density Distribution difference is relatively not obvious.Therefore, SGS will cause very large detecting error about radioactive nuclide equally distributed hypothesis in each section of layer, TGS reconstructs the requirement that the distributed in three dimensions of nucleic in pail for used dressings exceeds again relevant criterion simultaneously, therefore STGS balances SGS and TGS well about the strengths and weaknesses in measuring accuracy and Measuring Time, and its practicality strengthens greatly.
Accompanying drawing explanation
Fig. 1 is the structural representation of measurement mechanism one embodiment that the inventive method adopts;
Fig. 2 is Fig. 1 embodiment device front elevation;
Fig. 3 is Fig. 1 embodiment universal stage schematic diagram;
Fig. 4 is Fig. 1 embodiment universal stage moving assembly schematic top plan view;
Fig. 5 is the FB(flow block) of the inventive method;
Fig. 6 is ring-type stress and strain model schematic diagram in pail for used dressings a certain section of layer;
Fig. 7 is the horizontal section schematic diagram of Fig. 6.
Embodiment
Elaborate to embodiments of the invention below, the present embodiment is implemented under premised on technical solution of the present invention, give detailed embodiment and concrete operating process, but protection scope of the present invention is not limited to following embodiment.
Embodiment
As shown in Figure 1, the present embodiment comprises: pail for used dressings universal stage 1, universal stage moving assembly 2, detector hoistable platform assembly 3, transmission source hoistable platform assembly 4, pedestal 5, there is the high purity germanium detector 7 of collimating apparatus 6, there is transmission source 8 and the data processing module 9 of shielding slab, wherein: universal stage moving assembly 2, detector hoistable platform assembly 3 and transmission source hoistable platform assembly 4 are arranged on pedestal 5 jointly, pail for used dressings universal stage 1, high purity germanium detector 7 and transmission source 8 are arranged at universal stage moving assembly 2 respectively, on detector hoistable platform assembly 3 and transmission source hoistable platform assembly 4, and detector hoistable platform assembly 3 and transmission source hoistable platform assembly 4 are placed in the both sides of pail for used dressings universal stage 1 respectively, high purity germanium detector 7 produces electric signal and is connected with data processing module 9, this mechanical system can realize transmission source 8 and the precision lift of detector 7 and the rotation of pail for used dressings and translation.
As shown in Figure 3, described pail for used dressings universal stage 1 comprises: with the first servomotor 11 of the first speed reduction unit 10, universal stage support 12, universal stage base plate 13, universal stage axle sleeve 14, universal stage main shaft 15, universal stage swivel plate 16, universal stage shaft coupling 17, thrust ball bearing 18, angle thrust ball bearing 19, wherein: universal stage base plate 13 is connected with universal stage support 12, first servomotor 11 is connected with the first speed reduction unit 10, first speed reduction unit 10 is connected with universal stage main shaft 15 by universal stage shaft coupling 17, universal stage main shaft 15 is connected with universal stage swivel plate 16, thrust ball bearing 18 and angle thrust ball bearing 19 is respectively equipped with between universal stage main shaft 15 and universal stage axle sleeve 14, for supporting universal stage swivel plate 16 and preventing from toppling, when the first servomotor 11 with the first speed reduction unit 10 rotates, rotated by universal stage shaft coupling 17 and universal stage main shaft 15 driven rotary platform swivel plate 16, and drive the tested pail for used dressings be placed on universal stage swivel plate 16 to rotate.
As shown in Figure 4, described universal stage moving assembly 2 comprises: the second servomotor 20, first ball-screw 21, first guide rail 22, first base 23 and shaft coupling 24, wherein: the first guide rail 22 is arranged on the first base 23, the rotating shaft of the second servomotor 20 is connected with the first ball-screw 21 by shaft coupling 24, and the nut on the first ball-screw 21 is connected with universal stage base plate 13; When the second servomotor 20 rotates, drive the first ball-screw 21 to rotate and realized the movement in testee horizontal direction by feed screw nut drive pail for used dressings universal stage 1.
As shown in Figure 2, described detector hoistable platform assembly 3 comprises: detector carriage 25, detector platform base 26, with the first flat board 27 of floor, second flat board 28, second ball-screw 29, second guide rail 30, 3rd ball-screw 31, 3rd guide rail 32, hand round wheel 33 and the 3rd servomotor 35 with the second speed reduction unit 34, wherein: detector carriage 25 is fixedly installed on detector platform base 26, second guide rail 30 is arranged in detector carriage 25, 3rd servomotor 35 drives the second ball-screw 29 to rotate by the second speed reduction unit 34 and drives the first dull and stereotyped 27 liftings, 3rd guide rail 32 is arranged on the first flat board 27, second flat board 28 is connected with the 3rd ball-screw 31 and is parallel to the first flat board 27, hand round wheel 33 is connected with the 3rd ball-screw 31 and drives the second dull and stereotyped 28 translations, high purity germanium detector 7 is placed on the second flat board 28.
As shown in Figure 2, described transmission source hoistable platform assembly 4 comprises: transmission source support 36, transmission source platform base 37, the 3rd flat board 38, the 4th ball-screw 39, the 4th guide rail 40 and the 4th servomotor 42 with the 3rd speed reduction unit 41 with floor, wherein: transmission source support 36 is fixedly installed on transmission source platform base 37,4th guide rail 40 is arranged on transmission source support 36,4th servomotor 42 drives the 4th ball-screw 39 to rotate by the 3rd speed reduction unit 41 and drives the 3rd dull and stereotyped 38 liftings, and transmission source 8 is placed on the 3rd flat board 38.
The process flow diagram of the inventive method shown in Fig. 5, specific as follows:
The inventive method realizes STGS scanning by following concrete steps:
The first step, second dull and stereotyped 28 and the 3rd elemental height position of flat board 38 are set, make the detector 7 on the second flat board 28 aim at the bottom of pail for used dressings; Adjustment high purity germanium detector 7 and collimating apparatus 6 thereof on the second flat board 28, the particular location of transmission source 8 on the 3rd flat board 38, make detector 7 axis aim at transmission source 8 collimating aperture.
Second step, carry out the scanning of present segment layer
Pail for used dressings at the uniform velocity rotates, and rotating speed is about 10 revs/min, and the concrete Measuring Time of a measuring position is determined with radioactive level, is generally 5-10 minute, gathers the gamma-spectrometric data of a detecting location; Make pail for used dressings center be followed successively by 8 distances (such as 0,3.5,7.0,10.5,14.0,17.5,21.0,24.5cm) of specifying to the distance of detector 7 axis, altogether gather 8 gamma-spectrometric datas of this section of layer.
3rd step, in the vertical direction simultaneously mobile second dull and stereotyped 28 and the 3rd flat board 38, scan the every one deck of pail for used dressings from below to up, mobile 9 times, each vertical range 10cm, every layer of scanning all repeats second step.
4th step, data processing.
Be divided into two contents: transmission reconstruction and transmitting are rebuild, wherein transmission reconstruction is the computational analysis carried out the attenuation coefficient of ray or density to obtain pail for used dressings each section of layer filler, and launching reconstruction is the computational analysis carried out to obtain radionuclide specific activity distribution in pail for used dressings.
(1) transmission reconstruction
The method is identical with SGS, thinks that material is uniformly distributed in each layer.If P iequal detector 7 i-th (i=1,2 ..., I) and the transmissivity that records when being zero of individual section layer position eccentric position: P i=C i/ C max, wherein: C ithe gamma photons full energy peak counting rate that when indicating that pail for used dressings exists, detector 7 records i-th section layer position; C maxthe γ photon full energy peak counting rate that when representing that the gamma-rays that transmission source 8 sends is not decayed by sample, detector 7 records.The pass of transmissivity and attenuation coefficient is: μ id=-ln (P i), wherein μ ibe that in i-th section layer, material is to the attenuation coefficient of ray, D is pail for used dressings diameter.
(2) reconstruction is launched
Decay owing to all will produce with matter interaction in bucket before the ray arrival detector 7 that radioactive nuclide in bucket sends, therefore must carry out correction for attenuation.
Each section of layer ring-type Meshing Method schematic diagram shown in Fig. 6, Fig. 7, assuming that nucleic is uniformly distributed in each grid.Stress and strain model adopts equal area partition method, and the n-th ring radium computing method is: wherein: n=1,2 ..., N, N are the grid number divided, and R is pail for used dressings radius.
When detector is just to i-th section layer jth eccentric position, in m layer n-th ring-type grid, radioactive nuclide sends ray and is detected the counting rate that device 7 records and is: wherein α is the branching ratio of considered ray energy, ε mn, ijbe that in m layer n-th ring-type grid, radioactive nuclide is to the detection efficiency of detector 7 when being in i-th section layer jth eccentric position, this detection efficiency is mainly relevant with geometric position, detector 7 intrinsic conversion efficiency; A mnit is radionuclide specific activity in m layer n-th ring-type grid; Attenuation correction coefficient χ mn, ij=exp (-Σ ul), μ and l each layer attenuation coefficient that to be m layer n-th ring-type grid experience to detector 7 and average track lenth.Consider that detector can record the ray that all grids send, the counting rate that the detector 7 when being in i-th section layer jth eccentric position records is: in conjunction with the detection of all positions, can form unknown number number is I × N, and equation number is the system of linear equations of I × J:
Wherein, P=I × J, Q=I × N, e=α ε χ, the positional number (i.e. equation number) usually measured is no less than unknown number number (grid number namely divided), P >=Q.The method solving this system of linear equations is generally the alternative manner based on probability statistics, as maximum likelihood function process of iteration (Maximum Likelihood-ExpectationMaximization Algorithm) etc.
By to this solving equations, the activity that can obtain radioactive nuclide in pail for used dressings along the distribution of direction, bucket footpath and short transverse.Summation obtains the total activity of whole pail for used dressings
Above specific embodiments of the invention are described.It is to be appreciated that the present invention is not limited to above-mentioned particular implementation, those skilled in the art can make various distortion or amendment within the scope of the claims, and this does not affect flesh and blood of the present invention.

Claims (10)

1. the half tomographic gamma scan method that cold waste bucket is measured in a kind, the scanister that the method adopts comprises universal stage, detector platform, there is the detector of collimating apparatus, transmission source platform, transmission source and shield member thereof, analysis module, it is characterized in that, described radioactive waste bucket at the uniform velocity rotates when scanning survey, in bucket, radioactive nuclide relative bucket external detector after rotating is equivalent to annular line source by point source, pail for used dressings is divided some sections of layers vertically, each section of layer inner stuffing matter is uniformly distributed, some ring-type grids are divided again by each section of layer, measured by some eccentric positions of detector in each section of layer, in each ring-type grid of reconstruction calculating acquisition, radionuclide specific activity is along the radial and axial distribution of pail for used dressings, realize quick to the radioactivity of pail for used dressings, measure accurately.
2. half tomographic gamma scan method of middle cold waste bucket measurement according to claim 1, is characterized in that, specifically comprise the following steps:
The first step, adjustment detector and the particular location of collimating apparatus, transmission source and shield member thereof thereof, make detector axis aim at pail for used dressings center and by transmission source collimating aperture;
Second step, carry out the scanning of current layer
Pail for used dressings at the uniform velocity rotates with certain rotating speed, gathers gamma-spectrometric data; Make pail for used dressings center be followed successively by predetermined distance to the distance of detector axis, altogether gather several gamma-spectrometric datas of this section of layer;
3rd step, by detector platform and transmission source platform from the pail for used dressings bottom, move transmission source platform and detector platform in the vertical direction simultaneously, successively scan, every layer of scanning all repeats second step;
4th step, data processing
First the transmission measurement of each section of layer is carried out, obtain this section of layer material to the mean attenuation coefficient of ray, secondly each section of layer is divided the ring-type grid of homalographic along radial direction, calculate the detection efficiency through material correction for attenuation of each grid to detector, the system of equations of Detector count rate mutual relationship when setting up each ring-type grid radionuclide specific activity of reflection and be in each detecting location, solving equation group obtains radionuclide specific activity distribution along direction, bucket footpath and short transverse in pail for used dressings, and summation obtains the total activity of radioactive nuclide in pail for used dressings.
3. half tomographic gamma scan method of middle cold waste bucket measurement according to claim 2, it is characterized in that, in described second step, pail for used dressings at the uniform velocity rotates with certain rotating speed, and a concrete Measuring Time measuring position being gathered to its gamma-spectrometric data is determined with radioactive level.
4. half tomographic gamma scan method of middle cold waste bucket measurement according to claim 2, it is characterized in that, the data processing of described 4th step comprises transmission reconstruction and launches rebuilds, wherein transmission reconstruction is the computational analysis carried out the attenuation coefficient of ray or density to obtain pail for used dressings each section of layer filler, and launching reconstruction is the computational analysis carried out to obtain radionuclide specific activity distribution in pail for used dressings.
5. half tomographic gamma scan method of middle cold waste bucket measurement according to claim 4, it is characterized in that, the concrete grammar of described transmission reconstruction is:
Think that material is uniformly distributed in each layer, if P iequal the transmissivity that detector records when i-th section layer position eccentric position is zero: P i=C i/ C max, wherein: i=1,2 ..., I, C ithe gamma photons full energy peak counting rate that when indicating that pail for used dressings exists, detector records i-th section layer position; C maxthe γ photon full energy peak counting rate that when representing that the gamma-rays that transmission source sends is not decayed by sample, detector records, the pass of transmissivity and attenuation coefficient is: μ id=-ln (P i), wherein μ ibe that in i-th section layer, material is to the attenuation coefficient of ray, D is pail for used dressings diameter.
6. half tomographic gamma scan method of middle cold waste bucket measurement according to claim 4, is characterized in that, the described concrete grammar rebuild of launching is:
Decay owing to all will produce with matter interaction in bucket before the ray arrival detector that radioactive nuclide in bucket sends, therefore correction for attenuation must be carried out, when detector is just to i-th section layer jth eccentric position, in m layer n-th ring-type grid, radioactive nuclide sends ray and is detected the counting rate that device records and is: C mn, ij=α ε mn, ijχ mn, ija mn, wherein α is the branching ratio of considered ray energy, ε mn, ijbe in m layer n-th ring-type grid radioactive nuclide to the detection efficiency of detector when being in i-th section layer jth eccentric position; A mnit is radionuclide specific activity in m layer n-th ring-type grid; Attenuation correction coefficient χ mn, ij=exp (-Σ ul), μ and l each layer attenuation coefficient that to be m layer n-th ring-type grid experience to detector and average track lenth, consider that detector can record the ray that in whole pail for used dressings, all grids send, the counting rate that detector when being in i-th section layer jth eccentric position records is: in conjunction with the detection of all positions, composition unknown number number is I × N, and equation number is the system of linear equations of I × J:
Wherein, P=I × J, Q=I × N, e=α ε χ, I, J are integer, solve this system of linear equations, and obtain the distribution along direction, bucket footpath and short transverse in pail for used dressings of the activity of radioactive nuclide, summation obtains the total activity of whole pail for used dressings A = Σ 1 ≤ q ≤ Q A q .
7. half tomographic gamma scan method of middle cold waste bucket measurement according to claim 6, it is characterized in that, pail for used dressings segments I is 9, and eccentric position number J span is 2 to 8, and the ring-type grid number N of each section of layer is not more than J.
8. half tomographic gamma scan method of middle cold waste bucket measurement according to claim 7, it is characterized in that, the ring-type grid number N of each section of layer is identical with eccentric position number J.
9. half tomographic gamma scan method of middle cold waste bucket measurement according to claim 6, is characterized in that the positional number of described measurement and equation number are no less than the grid number that namely unknown number number divides, i.e. P >=Q.
10. the half tomographic gamma scan method measured of middle cold waste bucket according to claim 6, is characterized in that, the method solving this system of linear equations is the alternative manner based on probability statistics.
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Cited By (23)

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Publication number Priority date Publication date Assignee Title
CN105242298A (en) * 2015-09-07 2016-01-13 上海交通大学 Transmission source storage and automatic adjusting device and radioactive waste detection system
CN106611072A (en) * 2015-10-26 2017-05-03 中广核工程有限公司 Method and system for simulating radiation dose field of nuclear power station
CN106772529A (en) * 2016-11-28 2017-05-31 北京格物时代科技发展有限公司 A kind of dose of radiation remains activity value monitoring method and system
CN106843292A (en) * 2017-03-23 2017-06-13 四川理工学院 The motion control method and system of a kind of radioactive solid waste bucket detection means
CN108919331A (en) * 2018-07-03 2018-11-30 上海交通大学 A kind of double detector spiral gamma scanning survey method of pair of radioactive waste bucket
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Citations (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH07159541A (en) * 1993-12-08 1995-06-23 Toshiba Corp Radioactivity concentration measuring apparatus for radioactive waste container
JPH08220238A (en) * 1995-02-13 1996-08-30 Mitsubishi Heavy Ind Ltd Nondestructive collimator measuring method for radioactivity of radioactive waste solidified body canned in drum
US20080084960A1 (en) * 2006-07-13 2008-04-10 Stephen Croft Extending the Dynamic Range of the TGS Through the Use of a Dual Intensity Transmission Beam
CN102135625A (en) * 2010-12-21 2011-07-27 上海交通大学 Dual-detector segmenting gamma-scanning measuring device and scanning method thereof
CN102253401A (en) * 2011-04-28 2011-11-23 上海交通大学 Mechanical device used for scanning measurement of chromatographic Gamma
CN103245681A (en) * 2013-05-10 2013-08-14 中国原子能科学研究院 Neutron gamma combined measuring equipment
CN103308534A (en) * 2012-03-14 2013-09-18 中国原子能科学研究院 Chromatographic gamma scanning measurement method
CN103424762A (en) * 2013-07-25 2013-12-04 中国原子能科学研究院 Standard source for radioactive waste barrel segmenting gamma scanning device scales
CN103901052A (en) * 2014-03-19 2014-07-02 中国原子能科学研究院 SGS (Segmented Gamma-ray Scanner) and TGS (Tomographic Gamma Scanning) combined measurement device and optimization method of collimator

Patent Citations (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH07159541A (en) * 1993-12-08 1995-06-23 Toshiba Corp Radioactivity concentration measuring apparatus for radioactive waste container
JPH08220238A (en) * 1995-02-13 1996-08-30 Mitsubishi Heavy Ind Ltd Nondestructive collimator measuring method for radioactivity of radioactive waste solidified body canned in drum
US20080084960A1 (en) * 2006-07-13 2008-04-10 Stephen Croft Extending the Dynamic Range of the TGS Through the Use of a Dual Intensity Transmission Beam
CN102135625A (en) * 2010-12-21 2011-07-27 上海交通大学 Dual-detector segmenting gamma-scanning measuring device and scanning method thereof
CN102253401A (en) * 2011-04-28 2011-11-23 上海交通大学 Mechanical device used for scanning measurement of chromatographic Gamma
CN103308534A (en) * 2012-03-14 2013-09-18 中国原子能科学研究院 Chromatographic gamma scanning measurement method
CN103245681A (en) * 2013-05-10 2013-08-14 中国原子能科学研究院 Neutron gamma combined measuring equipment
CN103424762A (en) * 2013-07-25 2013-12-04 中国原子能科学研究院 Standard source for radioactive waste barrel segmenting gamma scanning device scales
CN103901052A (en) * 2014-03-19 2014-07-02 中国原子能科学研究院 SGS (Segmented Gamma-ray Scanner) and TGS (Tomographic Gamma Scanning) combined measurement device and optimization method of collimator

Non-Patent Citations (5)

* Cited by examiner, † Cited by third party
Title
刘诚 等: "核废物桶放射性探测的层析γ扫描技术", 《上海交通大学学报》 *
肖雪夫 等: "用于固体放射性废物无损定量测量的TGS图像重构技术", 《辐射防护》 *
阳刚 等: "桶装核废物层析γ扫描技术研究", 《核电子学与探测技术》 *
隋洪志 等: "γ无损测量技术在放射性废物检测中应用", 《2007年核化工三废处理处置学术交流会-厦门》 *
顾卫国 等: "放射性废物层析γ扫描动网络重建技术分析", 《上海交通大学学报》 *

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