CN109031386A - Radioactive substance method of counting and whole-body counter system - Google Patents
Radioactive substance method of counting and whole-body counter system Download PDFInfo
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- CN109031386A CN109031386A CN201811056561.8A CN201811056561A CN109031386A CN 109031386 A CN109031386 A CN 109031386A CN 201811056561 A CN201811056561 A CN 201811056561A CN 109031386 A CN109031386 A CN 109031386A
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- 239000000941 radioactive substance Substances 0.000 title claims abstract description 123
- 238000000034 method Methods 0.000 title claims abstract description 30
- 238000001228 spectrum Methods 0.000 claims abstract description 151
- 229910052732 germanium Inorganic materials 0.000 claims abstract description 125
- GNPVGFCGXDBREM-UHFFFAOYSA-N germanium atom Chemical compound [Ge] GNPVGFCGXDBREM-UHFFFAOYSA-N 0.000 claims abstract description 125
- 238000001514 detection method Methods 0.000 claims abstract description 42
- FVAUCKIRQBBSSJ-UHFFFAOYSA-M sodium iodide Chemical compound [Na+].[I-] FVAUCKIRQBBSSJ-UHFFFAOYSA-M 0.000 claims abstract description 36
- 238000012544 monitoring process Methods 0.000 claims abstract description 19
- 239000012857 radioactive material Substances 0.000 claims abstract description 12
- 235000009518 sodium iodide Nutrition 0.000 claims abstract description 12
- 230000005855 radiation Effects 0.000 claims abstract description 8
- 239000000126 substance Substances 0.000 claims description 18
- 230000000149 penetrating effect Effects 0.000 claims description 7
- 238000012937 correction Methods 0.000 claims description 6
- 230000033001 locomotion Effects 0.000 claims description 6
- 239000011159 matrix material Substances 0.000 claims description 6
- 238000005259 measurement Methods 0.000 abstract description 6
- 238000013461 design Methods 0.000 description 9
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 8
- 229910052708 sodium Inorganic materials 0.000 description 8
- 239000011734 sodium Substances 0.000 description 8
- 230000008859 change Effects 0.000 description 7
- 238000010586 diagram Methods 0.000 description 7
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 description 6
- 229910052740 iodine Inorganic materials 0.000 description 6
- 239000011630 iodine Substances 0.000 description 6
- 210000004072 lung Anatomy 0.000 description 5
- 238000012545 processing Methods 0.000 description 3
- WTCBONOLBHEDIL-UHFFFAOYSA-M Sodium iodate Chemical compound [Na+].[O-]I(=O)=O WTCBONOLBHEDIL-UHFFFAOYSA-M 0.000 description 2
- 230000008901 benefit Effects 0.000 description 2
- 238000004590 computer program Methods 0.000 description 2
- 210000003608 fece Anatomy 0.000 description 2
- 235000013305 food Nutrition 0.000 description 2
- 230000006870 function Effects 0.000 description 2
- 230000005484 gravity Effects 0.000 description 2
- ICIWUVCWSCSTAQ-UHFFFAOYSA-M iodate Chemical compound [O-]I(=O)=O ICIWUVCWSCSTAQ-UHFFFAOYSA-M 0.000 description 2
- 230000008569 process Effects 0.000 description 2
- 238000010183 spectrum analysis Methods 0.000 description 2
- 241001465754 Metazoa Species 0.000 description 1
- 208000019155 Radiation injury Diseases 0.000 description 1
- 208000027418 Wounds and injury Diseases 0.000 description 1
- 238000004458 analytical method Methods 0.000 description 1
- 230000005540 biological transmission Effects 0.000 description 1
- 210000000481 breast Anatomy 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 210000000038 chest Anatomy 0.000 description 1
- 230000006872 improvement Effects 0.000 description 1
- 230000001678 irradiating effect Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000003287 optical effect Effects 0.000 description 1
- 210000000056 organ Anatomy 0.000 description 1
- 238000004321 preservation Methods 0.000 description 1
- 238000004451 qualitative analysis Methods 0.000 description 1
- 238000004445 quantitative analysis Methods 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 238000012827 research and development Methods 0.000 description 1
- 239000002689 soil Substances 0.000 description 1
- 230000017105 transposition Effects 0.000 description 1
- 210000002700 urine Anatomy 0.000 description 1
Classifications
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/16—Measuring radiation intensity
- G01T1/161—Applications in the field of nuclear medicine, e.g. in vivo counting
- G01T1/163—Whole body counters
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- Health & Medical Sciences (AREA)
- Engineering & Computer Science (AREA)
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- General Health & Medical Sciences (AREA)
- Medical Informatics (AREA)
- Nuclear Medicine, Radiotherapy & Molecular Imaging (AREA)
- Optics & Photonics (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Physics & Mathematics (AREA)
- High Energy & Nuclear Physics (AREA)
- Molecular Biology (AREA)
- Spectroscopy & Molecular Physics (AREA)
- Measurement Of Radiation (AREA)
Abstract
本发明提供了一种放射性物质计数方法和全身计数器系统。该方法用于对待测体体内放射性物质进行内照射监测，包括步骤：使用与高纯锗探测器上下错位的碘化钠探测器检测放射性物质能谱计数；计算放射性物质能谱计数初值；移动全部高纯锗探测器和碘化钠探测器使之换位并检测放射性物质能谱计数；计算放射性物质能谱计数；再次移动全部高纯锗探测器和碘化钠探测器使之再次换位并检测放射性物质能谱计数；计算放射性物质能谱计数。根据本发明的技术方案，能够有效的提高探测效率、缩短检测时间，同时提高探测器能量分辨率，并能有效的降低由于无同时采集到的背部数据引入的测量误差。
The invention provides a radioactive material counting method and a whole body counter system. The method is used for internal radiation monitoring of radioactive substances in the body to be tested, and includes the steps of: using a sodium iodide detector dislocated up and down with a high-purity germanium detector to detect the energy spectrum counting of radioactive substances; calculating the initial value of the energy spectrum counting of radioactive substances; moving Transpose all high-purity germanium detectors and sodium iodide detectors and detect radioactive material spectrum counts; calculate radioactive material spectrum counts; move all high-purity germanium detectors and sodium iodide detectors again to transpose them again And detect the spectrum count of radioactive substances; calculate the spectrum count of radioactive substances. According to the technical solution of the present invention, the detection efficiency can be effectively improved, the detection time can be shortened, the energy resolution of the detector can be improved at the same time, and the measurement error introduced by not having simultaneously collected back data can be effectively reduced.
Description
Technical field
The present invention relates to radiation detection and protection field more particularly to a kind of radioactive substance method of counting and whole body countings
Device system.
Background technique
Quick with Nuclear Science and Technology is flourished, and the staff or the public in radiation work place have can
Radioactive substance can be brought into vivo sucking, eating, by way of the entrance of wound or skin, and then the organ of human body is caused
Radiation injury.In addition, standard GB/T 1887-2002 is clearly stipulate that " reply may be by the work of radioactive substance internal pollution
Make the corresponding interior irradiation monitoring of personnel placement, to prove the validity of implemented safeguard procedures ".Therefore, it is necessary to a kind of effective
Detection means γ photon that these internal radionuclides are emitted or X-ray etc. be monitored, to carry out corresponding
Remedy measures and existing safeguard procedures are further improved.
It is that living body directly measures and excreta measures indirectly respectively at present there are mainly two types of detection method.Due to excreta
There are many difficulties during collection, preservation, processing urine sample or excrement etc. for the indirect method of measurement, and have analysis time
The disadvantages of length, program are more, estimation dosage uncertainty is big, it is usually less to be used.Meanwhile International Commission on Radiological Protection
(ICRP) it is also indicated that in No. 78 publication " personal monitoring irradiated in staff ", interior irradiation is monitored, it is usually preferential
Select mode measured directly.Currently, whole-body counter (whole body counter) system be directly measure it is most typical
Implementation method, whole-body counter are that directly the X-ray or γ that intracorporal radioactive substance is launched are taken in measurement outside human body
Thus ray carries out the device of the Qualitative and quantitative analysis of radionuclide, in order to realize the system, detector cells are most to close
One of difficult point of key.
It is respectively for whole body counting (including the positions such as lung, neck, head, joint portion) most common two kinds of detectors
Nal detector and high purity germanium detector.The two feature is had nothing in common with each other, and the detection efficient of Nal detector is visited than HpGe
It is superior to survey device, only about 2-5 minutes, and price is relatively low, the about cost of 1/5 high purity germanium detector, but HpGe
The energy resolution of detector is much higher than tens times of Nal detector, the measurement of multicore element is more suitable for, so usually all can
It is preferred that first choice of the high purity germanium detector as interior irradiation monitoring.But the detection efficient of high purity germanium detector is very low, leads to
4 high purity germanium detectors are often used only, lung once monitor and probably need 30 minutes, and 4 high purity germanium detectors are logical
It can be often placed on the positive side of human body, as shown in Figure 1, this design the counting for having given up other side back half, in addition, this
Kind design can be greatly reduced particular for women detected person energy resolution, and mainly women frontal breast thickness can be direct
Influence the value of the equivalent wall of the chest thickness of most important parameters in energy resolution.
Therefore, it is necessary to a kind of design of novel whole-body counter system detector and corresponding applicable energy spectrum analysis methods.
Summary of the invention
The main purpose of the present invention is to provide a kind of radioactive substance method of counting and whole-body counter systems, to solve
The low problem low with energy resolution of detection efficient of the existing technology.
According to the first aspect of the invention, a kind of radioactive substance method of counting is provided, for putting in body body to be measured
Penetrating property substance irradiates monitoring in carrying out, which is characterized in that comprising steps of body top to be measured high purity germanium detector is made to be located at first
It is upper so that body lower part to be measured high purity germanium detector be located at it is second the next so that body top to be measured Nal detector is located at the
Two is upper and detect the counting of radioactive substance power spectrum, so as to be located at first the next and detect and put for body lower part to be measured Nal detector
Penetrating property substance power spectrum counts, wherein first is upper upper the next corresponding with second corresponding to first position, second with the first bottom
In second position；Second upper radioactive substance power spectrum is counted as second upper and the second the next radioactive material mass-energy
Spectrum counts initial value, and the first the next radioactive substance power spectrum is counted as first upper and the first the next radioactive material mass-energy
Spectrum counts initial value；Mobile whole high purity germanium detector and Nal detector, so that body top to be measured high purity germanium detector is located at
Second is upper and detect the counting of radioactive substance power spectrum, so as to be located at first upper and detect for body top to be measured Nal detector
Radioactive substance power spectrum counts, so that body lower part to be measured high purity germanium detector is located at the first bottom and detects radioactive substance power spectrum
It counts, so that body lower part to be measured Nal detector is located at the second bottom and detects the counting of radioactive substance power spectrum；Calculate first
Upper, first the next, second upper, the second the next radioactive substance power spectrum counting；Mobile whole high purity germanium detectors again
And Nal detector, so as to be located at first upper and detect radioactive substance power spectrum meter for body top to be measured high purity germanium detector
Number so that body top to be measured Nal detector be located at second it is upper and detect radioactive substance power spectrum counting so that body to be measured
Lower part high purity germanium detector is located at the second bottom and detects the counting of radioactive substance power spectrum, so that body lower part to be measured sodium iodide detects
Device is located at the first bottom and detects the counting of radioactive substance power spectrum；Calculate the radioactive substance power spectrum of first position and second position
It counts.
Preferably, multiple high purity germanium detectors are arranged in body top to be measured and equal number of Nal detector, lower part are set
Set equal number of high purity germanium detector and equal number of Nal detector.
Preferably, two high purity germanium detectors and two Nal detectors are arranged in body top to be measured, and lower part is arranged two
High purity germanium detector and two Nal detectors are in matrix pattern interlaced arrangement, mobile for whole high purity germanium detectors and iodine
Change sodium detector to be rotated by 90 ° in the horizontal direction, mobile again is that identical direction of rotation is rotated by 90 ° again.
Preferably, radioactive substance method of counting further includes the standard power spectrum counted radioactive substance power spectrum with HpGe
It is compared to carry out index correction.
According to the second aspect of the invention, a kind of whole-body counter system is provided, for body body radioactivity to be measured
Substance irradiates monitoring in carrying out characterized by comprising high purity germanium detector is located at body upper and lower part to be measured, first
Begin detection state, and top high purity germanium detector is upper positioned at first, and lower part high purity germanium detector is located at the second bottom, in the first detection
State, top high purity germanium detector are located at second upper and detect the counting of radioactive substance power spectrum, and lower part high purity germanium detector is located at
First it is the next simultaneously detect the counting of radioactive substance power spectrum, detect state second, top high purity germanium detector be located at first it is upper simultaneously
It detects radioactive substance power spectrum to count, lower part high purity germanium detector is located at the second bottom and detects the counting of radioactive substance power spectrum；
Nal detector is located at body upper and lower part to be measured, and in initial detecting state, top Nal detector is located on second
The counting of radioactive substance power spectrum is simultaneously detected in position, and lower part Nal detector is located at the first bottom and detects radioactive substance power spectrum meter
Number, first detect state, top Nal detector be located at first it is upper and detect radioactive substance power spectrum counting, lower part iodate
Sodium detector is located at the second bottom and detects the counting of radioactive substance power spectrum, detects state, top Nal detector position second
Upper and detect radioactive substance power spectrum and count in second, it is the next and detect radioactive material that lower part Nal detector is located at first
Mass-energy spectrum counts；Mobile controller is moved to for controlling high purity germanium detector and Nal detector from initial detecting state
First detection state, and be moved to the second detection state from the first detection state, first it is upper with first it is the next correspond to first position,
Second upper and the second bottom is corresponding to second position；Power spectrum processor, for by high purity germanium detector and sodium iodide detection
The radioactive substance power spectrum counting of device detection is handled.
Preferably, power spectrum processor is used to count the second upper radioactive substance power spectrum upper and second as second
The next radioactive substance power spectrum counts initial value, the first the next radioactive substance power spectrum is counted upper and first as first
The next radioactive substance power spectrum counts initial value.
Preferably, power spectrum processor be used to count based on the radioactive substance power spectrum of the first detection state calculate it is first upper,
First is the next, second upper, the second the next radioactive substance power spectrum counting.
Preferably, power spectrum processor be used for based on second detection state radioactive substance power spectrum count calculate first position and
The radioactive substance power spectrum of second position counts.
Preferably, one or more high purity germanium detectors and equal number of Nal detector is arranged in body top to be measured,
Equal number of high purity germanium detector and equal number of Nal detector is arranged in lower part.
Preferably, two high purity germanium detectors and two Nal detectors are arranged in body top to be measured, and lower part is arranged two
High purity germanium detector and two Nal detectors are in matrix pattern interlaced arrangement, mobile for whole high purity germanium detectors and iodine
Change sodium detector to be rotated by 90 ° in the horizontal direction, mobile again is that identical direction of rotation is rotated by 90 ° again.
Optionally, a high purity germanium detector and a Nal detector is arranged in body top to be measured, and lower part is arranged one
High purity germanium detector and a Nal detector are in 8-shaped interlaced arrangement, mobile for whole high purity germanium detectors and sodium iodide
Detector rotates 180 degree in the horizontal direction, and mobile again is to rotate 180 degree again.
Optionally, three high purity germanium detectors and three Nal detectors are arranged in body top to be measured, and lower part is arranged three
High purity germanium detector and three Nal detectors, hexagonal interlaced arrangement are mobile for whole high purity germanium detectors and iodine
Change sodium detector to rotate by a certain angle in the horizontal direction, mobile again is that identical direction of rotation rotates equal angular again.
Optionally, the high purity germanium detector and Nal detector and the HpGe of lower part setting of body top setting to be measured
Detector and Nal detector are in alternating expression arrangement, and mobile is whole high purity germanium detectors and Nal detector in level
Direction rotates by a certain angle, so that the position for placing Nal detector originally becomes to place high purity germanium detector, originally places
The place of high purity germanium detector becomes to place Nal detector, and mobile again is that identical direction of rotation rotates same angular again
Degree.
Optionally, one or more high purity germanium detectors and one or more Nal detectors are set above body to be measured,
The detector of another type is arranged in same position below body to be measured, and mobile is that two detector positions exchange up and down at same position,
Mobile again is two detectors in same position or more location swap again.More specifically, all setting is high-purity by one side of body to be measured
Nal detector is all arranged in germanium detector, the same position of another party.
It compared with prior art, according to the technique and scheme of the present invention, can be in combination with Nal detector and HpGe
The advantage of both detectors uses detection efficient high used time short Nal detector monitoring result as high purity germanium detector
Initial value, the effective detection efficient that improves shorten detection time, while further being revised using the initial value of Nal detector high-purity
The monitoring result of germanium detector improves detector energy resolution ratio；Using high purity germanium detector and Nal detector alternating expression
Design is placed, in the comparable situation of detector cost, the counting of 2 times of detector numbers is realized, further increases detector energy
Measure resolution ratio；Using the detector cells design of two groups of top and the bottom, effectively reduce due to drawing without collected back data simultaneously
The measurement error entered further improves system capacity resolution ratio.
Detailed description of the invention
The drawings described herein are used to provide a further understanding of the present invention, constitutes part of this application, this hair
Bright illustrative embodiments and their description are used to explain the present invention, and are not constituted improper limitations of the present invention.In the accompanying drawings:
Fig. 1 shows exemplary counts device detector position schematic diagram in the prior art；
Fig. 2 shows the flow charts of radioactive substance method of counting according to an embodiment of the present invention；
Fig. 3 shows the flow chart of radioactive substance method of counting according to another embodiment of the present invention；
Fig. 4 shows the schematic diagram of whole-body counter system according to an embodiment of the present invention；
Fig. 5 schematically shows general technical route schematic diagram according to an embodiment of the present invention；
Fig. 6 schematically shows collectivity Scheme Design schematic diagram according to the system in the embodiment of the present invention；
Fig. 7 schematically shows detector cells high purity germanium detector according to an embodiment of the present invention and sodium iodide detects
Device horizontal plane rotates angle schematic diagram；
Fig. 8 schematically shows two groups of detector cells in top and the bottom according to an embodiment of the present invention and search coverage data
Corresponding schematic diagram；
Fig. 9 schematically shows utilization HpGe standard power spectrum according to an embodiment of the present invention to HpGe and sodium iodide
Superimposed power spectrum carries out index correction schematic diagram.
In the drawings, the same or similar part is indicated using identical reference label.
Specific embodiment
To make the object, technical solutions and advantages of the present invention clearer, below in conjunction with drawings and the specific embodiments, to this
Invention is described in further detail.
In the following description, the reference of " one embodiment ", " embodiment ", " example ", " example " etc. is shown
The embodiment or example so described may include special characteristic, structure, characteristic, property, element or limit, but not each reality
Applying example or example all necessarily includes special characteristic, structure, characteristic, property, element or limit.In addition, reusing phrase " one
In a embodiment " although it is possible to be to refer to identical embodiment, but be not necessarily referring to identical embodiment.
For the sake of simplicity, some technical features known to those skilled in the art are omitted in being described below.
It is put Fig. 2 shows according to an embodiment of the present invention for irradiation monitoring in being carried out to body body radioactivity substance to be measured
Penetrating property substance method of counting 200.
Radioactive substance method of counting 200 includes initial detecting step 202, initial calculating step 204, the first detecting step
206, first step 208, the second detecting step 210, second calculating step 212 are calculated.
In initial detecting step 202, so that body top to be measured high purity germanium detector is upper positioned at first, so that body to be measured
Lower part high purity germanium detector be located at it is second the next so as to be located at second upper and detect radiation for body top to be measured Nal detector
Property substance power spectrum count so as to be located at first the next and detect radioactive substance power spectrum meter for body lower part to be measured Nal detector
It counts, wherein first upper and the first bottom is corresponding to first position, second upper and the second bottom is corresponding to second position.Letter and
Yan Zhi, initial detecting step 202 detect radioactive material mass-energy using the Nal detector to misplace up and down with high purity germanium detector
Spectrum counts.
Preferably, one or more high purity germanium detectors and equal number of Nal detector is arranged in body top to be measured,
Equal number of high purity germanium detector and equal number of Nal detector is arranged in lower part.
In initial calculating step 204, the second upper radioactive substance power spectrum is counted upper and second as second
The next radioactive substance power spectrum counts initial value, the first the next radioactive substance power spectrum is counted upper and first as first
The next radioactive substance power spectrum counts initial value.Namely the radioactive substance power spectrum based on the detection of initial detecting step 202 counts
The radioactive substance power spectrum for calculating first position and second position counts initial value.
In the first detecting step 206, mobile whole high purity germanium detector and Nal detector, so that body top to be measured
High purity germanium detector be located at second it is upper and detect radioactive substance power spectrum counting so that body top Nal detector position to be measured
It is upper and detect radioactive substance power spectrum and count in first, so as to be located at first the next and examine for body lower part to be measured high purity germanium detector
It surveys radioactive substance power spectrum to count, so that body lower part to be measured Nal detector is located at the second bottom and detects radioactive material mass-energy
Spectrum counts.In brief, the mobile whole high purity germanium detectors of the first detecting step 206 and Nal detector are allowed to replace and examine
Radioactive substance power spectrum is surveyed to count.
It is calculated in step 208 first, calculates first upper, first the next, second upper, the second the next radioactive material
Mass-energy spectrum counts.Namely initial value and the first detecting step are counted based on the radioactive substance power spectrum of first position and second position
The radioactive substance power spectrum of 206 detections counts the radioactive substance power spectrum counting for calculating first position and second position.
In the second detecting step 210, whole high purity germanium detectors and Nal detector are moved again, so that body to be measured
Top high purity germanium detector be located at first it is upper and detect radioactive substance power spectrum counting so that body top to be measured sodium iodide detect
Device be located at it is second upper and detect the counting of radioactive substance power spectrum so as to be located at second the next for body lower part to be measured high purity germanium detector
And the counting of radioactive substance power spectrum is detected, so that body lower part to be measured Nal detector is located at the first bottom and detects radioactive material
Mass-energy spectrum counts.In brief, mobile whole high purity germanium detectors and Nal detector are allowed to the second detecting step 210 again
It replaces again and detects the counting of radioactive substance power spectrum.
Preferably, two high purity germanium detectors and two Nal detectors are arranged in body top to be measured, and lower part is arranged two
High purity germanium detector and two Nal detectors are in matrix pattern interlaced arrangement, mobile for whole high purity germanium detectors and iodine
Change sodium detector to be rotated by 90 ° in the horizontal direction, mobile again is that identical direction of rotation is rotated by 90 ° again.
It is calculated in step 212 second, the radioactive substance power spectrum for calculating first position and second position counts.Namely base
It is counted and the second detecting step in the radioactive substance power spectrum that first calculates the first position that step 208 calculates and second position
The radioactive substance power spectrum of 210 detections counts the radioactive substance power spectrum counting for calculating first position and second position.
Preferably, radioactive substance method of counting 200 further includes after the second calculating step 212 by radioactive substance power spectrum
Counting is compared to carry out index correction with the standard power spectrum of HpGe.
Fig. 3 shows putting for irradiation monitoring in carrying out to body body radioactivity substance to be measured for another embodiment of the present invention
Penetrating property substance method of counting 200 '.Theoretically, complete data can be obtained by detection twice as shown in Figure 2, but still can basis
To the actual demand of counting (such as requiring higher precision) in different application, it is determined whether carry out subsequent n-th detecting step and
N-th calculates step, wherein n >=3, and schematically showing in Fig. 3 terminates after even number calculates step, but those skilled in the art
It is understood that can also terminate after odd number calculates step.
Fig. 4 shows according to an embodiment of the present invention for irradiating the complete of monitoring in carrying out to body body radioactivity substance to be measured
Body counter system 300.
Whole-body counter system 300 include high purity germanium detector 302, Nal detector 304, mobile controller 306,
Power spectrum processor 308.
High purity germanium detector 302 is located at body upper and lower part to be measured, in initial detecting state, top high purity germanium detector
Upper positioned at first, lower part high purity germanium detector is located at second the next, detects state first, and top high purity germanium detector is located at the
Two is upper and detect the counting of radioactive substance power spectrum, and it is the next and detect radioactive material mass-energy that lower part high purity germanium detector is located at first
Spectrum count, second detect state, top high purity germanium detector be located at first it is upper and detect radioactive substance power spectrum counting, lower part
High purity germanium detector is located at the second bottom and detects the counting of radioactive substance power spectrum.
Nal detector 304 is located at body upper and lower part to be measured, in initial detecting state, top Nal detector
Upper and detect radioactive substance power spectrum and count positioned at second, it is the next and detect radioactivity that lower part Nal detector is located at first
Substance power spectrum counts, and detects state first, it is upper and detect radioactive substance power spectrum meter that top Nal detector is located at first
Number, lower part Nal detector are located at the second bottom and detect the counting of radioactive substance power spectrum, detect state, top iodate second
Sodium detector is located at second upper and detect the counting of radioactive substance power spectrum, and it is the next and examine that lower part Nal detector is located at first
Radioactive substance power spectrum is surveyed to count.In brief, Nal detector 304 and about 302 high purity germanium detector misplace.
Preferably, multiple high purity germanium detectors are arranged in body top to be measured and equal number of Nal detector, lower part are set
Set equal number of high purity germanium detector and equal number of Nal detector.
Mobile controller 306 is moved for controlling high purity germanium detector 302 and Nal detector 304 from initial detecting state
It moves to the first detection state, and is moved to the second detection state from the first detection state, first upper and the first bottom is corresponding to first
Position, second upper and the second bottom is corresponding to second position.In brief, mobile controller 306 controls HpGe detection
Device 302 and the mobile transposition of Nal detector 304.
Preferably, two high purity germanium detectors and two Nal detectors are arranged in body top to be measured, and lower part is arranged two
High purity germanium detector and two Nal detectors are in matrix pattern interlaced arrangement, mobile for whole high purity germanium detectors and iodine
Change sodium detector to be rotated by 90 ° in the horizontal direction, mobile again is that identical direction of rotation is rotated by 90 ° again.
Power spectrum processor 308 is used for the radioactive substance detected by high purity germanium detector 302 and Nal detector 304
Power spectrum counting is handled.
Preferably, power spectrum processor 308 be used to count the second upper radioactive substance power spectrum as second it is upper and
Second the next radioactive substance power spectrum counts initial value, by the first the next radioactive substance power spectrum count as first it is upper and
First the next radioactive substance power spectrum counts initial value.Further, power spectrum processor 308 is used for putting based on the first detection state
Penetrating property substance power spectrum, which counts, calculates first upper, first the next, second upper, the second the next radioactive substance power spectrum counting.
Further, power spectrum processor 308, which is used to count based on the radioactive substance power spectrum of the second detection state, calculates first position and the
The radioactive substance power spectrum at two positions counts.
It will be appreciated by those skilled in the art that although in order to make it easy to understand, get off to describe positional relationship above in the application,
Such as it is top, lower part, upper, the next, but be not limited to that upper and lower on gravity direction or vertical direction, connotation can be with
It is extended to the opposite sides of body to be measured, such as top to bottom, left and right, front and rear etc..Similarly, horizontal direction described herein also not office
It is limited to the plane perpendicular to gravity direction or vertical direction, but connotation is extended to the vertical plane relative to upper and lower orientation.
Present system collectivity Scheme Design is as shown in figure 5, mainly include three chief components: measuring device system
System, kinetic control system, software analysis process system.
Measuring device system is the most crucial part of whole-body counter system, is mainly consisted of two parts, detector and
Data acquisition and gamma-spectrometric data are handled.
Detector is the component part of measuring device system most critical, below with each two pairs of high purity germanium detectors and iodine up and down
Change sodium detector and illustrates technical solution of the present invention to illustrate.As shown in fig. 6, the present invention proposes to distinguish position by two groups of detector cells
In the upper and lower for being detected human body, wherein one group of detector cells is by two high purity germanium detectors and two Nal detectors
Composition, high purity germanium detector is staggeredly placed with Nal detector, side view as shown in fig. 6, top view as shown in fig. 7, iodate
Sodium detector is identical as the size of high purity germanium detector, i.e. the data of Nal detector acquisition can be in the same acquisition position
Initial value is used as HpGe detection.Rack, supply convertor, motion controller, servo-driver, motor etc. are omitted in Fig. 6
Control parts of motion and refrigerating plant for high purity germanium detector.Specifically, when detection, by two groups of top and the bottom detector list
Member is placed on interested monitoring position, as shown in figure 8, such as head, neck, lung, joint part.
Data acquisition and gamma-spectrometric data, which are handled, mainly to be realized by four steps:
The first step, the determination of detector initial value.In order to guarantee that there is Nal detector in tetra- regions RA, RB, RC and RD
Initial value, if the upper and lower surface in a region is all high purity germanium detector, you can't get sodium iodide detections in the region
The initial value of device, so the same detector position, the above is high purity germanium detector, and here is Nal detector, or conversely,
It deliberately will dislocation design up and down in this way.No. 1, No. 2, No. 3, No. 4, No. 1', No. 2', No. 3', 4' detector are put according to Fig. 8
Station acquisition 2 minutes, acquisition will be placed on a, b, c, d, a', b', c', the initial value of this 8 area detector power spectrums of d',
In, the data that No. 2 and No. 3 detectors are acquired acquire No. 1' and 4' detector as the initial value in the region b and the region c
Initial value of the data as the region a' and the region d'.Meanwhile No. 2, No. 3, No. 1', 4' detector acquisition data be also used as b',
The initial value in the region c', a, d, as shown in formula (1).
Upper detector unitLower part detector cells
Second step, the first time acquisition of detector data.In same plane, high purity germanium detector and Nal detector are handed over
Mistake arrangement is placed originally because the region for placing Nal detector originally needs to become high purity germanium detector after being rotated by 90 °
The region of high purity germanium detector needs to become Nal detector.Two groups of top and the bottom detector cells are rotated clockwise the simultaneously
1 90 degree of acquisitions a period of time, wherein the power spectrum of 1,2,3, No. 4 four detector of upper detector unit, which counts, is respectivelyThe power spectrum counting of lower part detector cells 1', 2', 3', No. 4' four detector is respectivelyAs shown in formula (2).
Upper detector unitLower part detector cells
Third step, second of acquisition of detector data and the processing for acquiring data for the first time, the two carry out simultaneously.It visits
Second of acquisition method therefor for surveying device data is similar with second step, and two groups of top and the bottom detector cells are rotated clockwise simultaneously
2nd 90 degree of acquisitions a period of time, wherein the power spectrum of 1,2,3, No. 4 four detector of upper detector unit, which counts, is respectivelyThe power spectrum counting of lower part detector cells 1', 2', 3', No. 4' four detector is respectivelyAs shown in formula (3).While detector acquires data, computer can be in second step
Collected counting is handled.
Upper detector unitLower part detector cells
Further, it carries out interested monitoring position to be divided into RA (R according to pickup areaa+Ra')、RB(Rb+Rb')、RC
(Rc+Rc')、RD(Rd+Rd') four parts, then, the interior irradiation monitoring acquired after rotating clockwise the 2nd 90 degree, which counts, is
Shown in formula (4)；And so on, the acquisition data of the 90 degree of acquisitions the 3rd time of rotation the 3rd rotate n-th of 90 degree of acquisition n-ths
Acquisition data.It illustrates, theoretically, rotating to the 2nd 90 degree can be obtained complete data, but still can be according to different application
The number of detector cells rotation is determined to the difference of count requirement.
After rotating the 2nd 90 degree
4th step, the processing of gamma-spectrometric data.The present invention proposes the power spectrum C after being overlappedH+NCarry out further scale
Correction, as shown in figure 9, by the standard power spectrum C of itself and HpGeRProgress index correction is compared and obtains final power spectrumAs shown in formula (5).
5th step, rotation or translates two groups of detector cells up and down, is monitored to next region of interest, repeats the
One step to the 4th step.
It is to be illustrated with each four detectors up and down above.As long as it will be appreciated by those skilled in the art that meeting same
The type of two detectors is different above and below position, such as top is high purity germanium detector, then lower section must be that sodium iodide is visited
Survey device.Conversely, top is Nal detector, then lower section must be high purity germanium detector.Four are selected mainly to consider
The cost of detector and the area coverage of lung.After detector number changes, the angle of rotation also will and then change, and need full
Foot: after once rotating, the position for placing high purity germanium detector originally is changed to placement Nal detector, places iodate originally
The position of sodium detector is changed to placement high purity germanium detector.
Kinetic control system of the invention will use a multivariant control platform, including software control system,
Major function is to adjust movement, the rotation etc. of two groups of detector cells, with the relative position for ensuring to pop one's head in and human body holding is suitable.
In addition, by using gear, rack gear, lead screw, worm screw and the worm-gear combination for having self-locking function, and the transmission combination can motor
Control can also carry out standby control manually.
Software analysis process system preferably uses the agent of the radionuclide intake according to No. 68 publication of ICRP
The interior irradiation of the parameters such as Committed effective dose caused by coefficient of discharge and standard GB/T 18871-2002 unit intake research and development
Dose assessment software.
The design of novel whole-body counter system detector and energy spectrum analysis method proposed by the present invention, will pacify for core and radiation
During core and radiation are met an urgent need in the case of the further refinement of full standard quantitative, accident the quick of internal dose, accurate measurements with
And Pb-210 in daily life public's food chain, the monitoring of the nucleic such as Po-210 are provided which strong technical foundation, meanwhile, this hair
The feature of bright low cost also can provide technological means for the further industrialization of whole-body counter system.
It should also be noted that the whole-body counter Dose Monitoring system that the present invention establishes is of wide application.This is
System cannot be only used for the research of Whole Body key position (lung, neck, head, joint portion etc.), could be applicable to animals and plants,
Radio nuclide monitoring system in the human foods chain such as soil.
It should be understood by those skilled in the art that, embodiments herein can provide as method, system or computer program
Product.Therefore, complete hardware embodiment, complete software embodiment or reality combining software and hardware aspects can be used in the application
Apply the form of example.Moreover, it wherein includes the computer of computer usable program code that the application, which can be used in one or more,
The computer program implemented in usable storage medium (including but not limited to magnetic disk storage, CD-ROM, optical memory etc.) produces
The form of product.
The above description is only an embodiment of the present invention, is not intended to restrict the invention, for those skilled in the art
For member, the invention may be variously modified and varied.All within the spirits and principles of the present invention, it is made it is any modification,
Equivalent replacement, improvement etc., should be included within scope of the presently claimed invention.
Claims (10)
1. a kind of radioactive substance method of counting, for irradiation monitoring in being carried out to body body radioactivity substance to be measured, feature
It is, comprising steps of
So that the body top to be measured high purity germanium detector is upper positioned at first, so that the body lower part to be measured high purity germanium detector
Positioned at the second bottom, so as to be located at second upper and detect radioactive substance power spectrum meter for the body top to be measured Nal detector
Number counts, wherein institute so that the body lower part to be measured Nal detector is located at the first bottom and detects radioactive substance power spectrum
It states first upper and described first bottom and corresponds to first position, described second upper and described second bottom is corresponding to second
Position；
Described second upper radioactive substance power spectrum is counted as described second upper and the second the next radioactive substance
Power spectrum counts initial value, and the described first the next radioactive substance power spectrum is counted and upper and the first bottom is put as described first
Penetrating property substance power spectrum counts initial value；
Mobile whole high purity germanium detector and Nal detector, so that the body top to be measured high purity germanium detector is positioned at described
Second it is upper and detect radioactive substance power spectrum counting so that the body top to be measured Nal detector be located at described first on
The counting of radioactive substance power spectrum is simultaneously detected in position, so that the body lower part to be measured high purity germanium detector is located at first bottom and examines
It surveys radioactive substance power spectrum to count, so that the body lower part to be measured Nal detector is located at second bottom and detects radiation
Property substance power spectrum count；
Calculate described first upper, the described first the next, described second upper, described second the next radioactive substance power spectrum meter
Number；
Mobile whole high purity germanium detectors and Nal detector again, so that the body top to be measured high purity germanium detector is located at
Described first is upper and detect the counting of radioactive substance power spectrum, so that the body top to be measured Nal detector is located at described the
Two is upper and detect the counting of radioactive substance power spectrum, so as to be located at described second the next for the body lower part to be measured high purity germanium detector
And the counting of radioactive substance power spectrum is detected, so that the body lower part to be measured Nal detector is located at first bottom and detects
Radioactive substance power spectrum counts；
The radioactive substance power spectrum for calculating the first position and the second position counts.
2. radioactive substance method of counting according to claim 1, which is characterized in that the body top setting to be measured is multiple
Equal number of high purity germanium detector and same number is arranged in high purity germanium detector and equal number of Nal detector, lower part
Nal detector.
3. radioactive substance method of counting according to claim 2, which is characterized in that the body top to be measured is arranged two
Two high purity germanium detectors and two Nal detectors are arranged in high purity germanium detector and two Nal detectors, lower part,
In matrix pattern interlaced arrangement, the movement is that whole high purity germanium detectors and Nal detector are rotated by 90 ° in the horizontal direction,
The movement again is that identical direction of rotation is rotated by 90 ° again.
4. radioactive substance method of counting according to claim 1, which is characterized in that further include by radioactive substance power spectrum
Counting is compared to carry out index correction with the standard power spectrum of HpGe.
5. a kind of whole-body counter system, for irradiation monitoring in being carried out to body body radioactivity substance to be measured, which is characterized in that
Include:
High purity germanium detector is located at the body upper and lower part to be measured, in initial detecting state, top high purity germanium detector position
Upper in first, lower part high purity germanium detector is located at the second bottom, detects state first, the top high purity germanium detector is located at
Second is upper and detect the counting of radioactive substance power spectrum, and it is the next and detect radioactivity that the lower part high purity germanium detector is located at first
Substance power spectrum counts, and detects state second, it is upper and detect radioactive material that the top high purity germanium detector is located at described first
Mass-energy spectrum counts, and the lower part high purity germanium detector is located at second bottom and detects the counting of radioactive substance power spectrum；
Nal detector is located at the body upper and lower part to be measured, in the initial detecting state, the detection of top sodium iodide
Device is located at second upper and detect the counting of radioactive substance power spectrum, and it is the next and detect radiation that lower part Nal detector is located at first
Property substance power spectrum count, it is described first detection state, the top Nal detector be located at described first it is upper and detect put
Penetrating property substance power spectrum counts, and the lower part Nal detector is located at second bottom and detects radioactive substance power spectrum meter
Number, in the second detection state, it is upper and detect radioactive substance power spectrum that the top Nal detector is located at described second
It counts, the lower part Nal detector is located at first bottom and detects the counting of radioactive substance power spectrum；
Mobile controller is moved for controlling the high purity germanium detector and the Nal detector from the initial detecting state
The first detection state is moved, and is moved to the second detection state, the described first upper and institute from the first detection state
It states the first bottom and corresponds to first position, described second upper and described second bottom corresponds to second position；
Power spectrum processor, for the radioactive substance power spectrum by the high purity germanium detector and Nal detector detection
Counting is handled.
6. whole-body counter system according to claim 5, which is characterized in that the power spectrum processor is used for described the
Two upper radioactive substance power spectrums are counted as described second upper and the second the next radioactive substance power spectrum counting initial value,
Described first the next radioactive substance power spectrum is counted as described first upper and the first the next radioactive substance power spectrum
Count initial value.
7. whole-body counter system according to claim 6, which is characterized in that the power spectrum processor is used for based on described
The radioactive substance power spectrum of first detection state count calculate it is described first upper, described first the next, described second upper, described
Second the next radioactive substance power spectrum counts.
8. whole-body counter system according to claim 7, which is characterized in that the power spectrum processor is used for based on described
The radioactive substance power spectrum of second detection state counts the radioactive substance power spectrum for calculating the first position and the second position
It counts.
9. whole-body counter system according to claim 5, which is characterized in that the body top to be measured is arranged one or more
Equal number of high purity germanium detector and identical number is arranged in a high purity germanium detector and equal number of Nal detector, lower part
Purpose Nal detector.
10. whole-body counter system according to claim 9, which is characterized in that two height are arranged in the body top to be measured
Pure germanium detector and two Nal detectors, lower part are arranged two high purity germanium detectors and two Nal detectors, are in
Matrix pattern interlaced arrangement, the movement are that whole high purity germanium detectors and Nal detector are rotated by 90 ° in the horizontal direction, institute
Stating mobile again is that identical direction of rotation is rotated by 90 ° again.
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111551690A (en) * | 2020-05-16 | 2020-08-18 | 成都理工大学 | Radioactive soil continuous sorting system and its control method |
| CN113466923A (en) * | 2020-03-31 | 2021-10-01 | 同方威视技术股份有限公司 | Method and apparatus for detecting radioactive substance |
Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1983001109A1 (en) * | 1981-09-25 | 1983-03-31 | Pollard, David, E. | In-vivo radiation counter |
| US4760260A (en) * | 1986-08-15 | 1988-07-26 | Westinghouse Electric Corp. | Diagnostic whole body counter |
| JPH03185382A (en) * | 1989-12-15 | 1991-08-13 | Fuji Electric Co Ltd | whole body counter |
| WO2012077468A1 (en) * | 2010-12-09 | 2012-06-14 | 独立行政法人理化学研究所 | Imaging device using gamma rays, image signal processor, and image processing method for gamma ray measurement data |
| CN102590848A (en) * | 2012-02-07 | 2012-07-18 | 成都理工大学 | Portable lung counting device |
| KR20130086429A (en) * | 2012-01-25 | 2013-08-02 | 한국수력원자력 주식회사 | Radiation measuring system based on optimal measurement geometry and method for measuring radiation |
| JP2014074701A (en) * | 2012-10-05 | 2014-04-24 | New Care Medical Systems Co Ltd | Open-type whole body radiation counter |
| US20140299784A1 (en) * | 2012-01-13 | 2014-10-09 | National Institute Of Radiological Sciences | Radioactive substance detection device, radiation source location visibility system, and radioactive substance detection method |
| JP2017044516A (en) * | 2015-08-25 | 2017-03-02 | 富士電機株式会社 | Radiation detection device |
-
2018
- 2018-09-11 CN CN201811056561.8A patent/CN109031386B/en active Active
Patent Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1983001109A1 (en) * | 1981-09-25 | 1983-03-31 | Pollard, David, E. | In-vivo radiation counter |
| US4760260A (en) * | 1986-08-15 | 1988-07-26 | Westinghouse Electric Corp. | Diagnostic whole body counter |
| JPH03185382A (en) * | 1989-12-15 | 1991-08-13 | Fuji Electric Co Ltd | whole body counter |
| WO2012077468A1 (en) * | 2010-12-09 | 2012-06-14 | 独立行政法人理化学研究所 | Imaging device using gamma rays, image signal processor, and image processing method for gamma ray measurement data |
| US20140299784A1 (en) * | 2012-01-13 | 2014-10-09 | National Institute Of Radiological Sciences | Radioactive substance detection device, radiation source location visibility system, and radioactive substance detection method |
| KR20130086429A (en) * | 2012-01-25 | 2013-08-02 | 한국수력원자력 주식회사 | Radiation measuring system based on optimal measurement geometry and method for measuring radiation |
| CN102590848A (en) * | 2012-02-07 | 2012-07-18 | 成都理工大学 | Portable lung counting device |
| JP2014074701A (en) * | 2012-10-05 | 2014-04-24 | New Care Medical Systems Co Ltd | Open-type whole body radiation counter |
| JP2017044516A (en) * | 2015-08-25 | 2017-03-02 | 富士電機株式会社 | Radiation detection device |
Non-Patent Citations (7)
| Title |
|---|
| DONG KEJUN ET AL.: "Methodological study on exposure date of Tiankeng by AMS measurement of in situ produced cosmogenic 36Cl" * |
| JONAS M. C. ET AL.: "Tests of HPGe- and scintillation-based backpack γ-radiation survey systems" * |
| NORA L. MAIDANA ET AL.: "Experimental HPGe coaxial detector response and efficiency compared to Monte Carlo simulations" * |
| 宋易阳 等: "多探头全身计数器探测效率随体模大小的变化及修正" * |
| 王红波: "核医学科工作人员职业性内照射研究" * |
| 肖运实: "基于Geant4的肺部计数器效率校准及其受核素分布影响研究" * |
| 靳芳 等: "电子束辐射对玉米及陆地棉花粉萌发率的影响" * |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113466923A (en) * | 2020-03-31 | 2021-10-01 | 同方威视技术股份有限公司 | Method and apparatus for detecting radioactive substance |
| CN113466923B (en) * | 2020-03-31 | 2024-04-12 | 同方威视技术股份有限公司 | Method and apparatus for detecting radioactive substance |
| CN111551690A (en) * | 2020-05-16 | 2020-08-18 | 成都理工大学 | Radioactive soil continuous sorting system and its control method |
| CN111551690B (en) * | 2020-05-16 | 2022-10-25 | 成都理工大学 | Radioactive soil continuous sorting system and its control method |
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