CN104360376A - Gamma camera having function of identifying radioactive source, namely nuclide, and nuclide identification method - Google Patents
Gamma camera having function of identifying radioactive source, namely nuclide, and nuclide identification method Download PDFInfo
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Abstract
The invention relates to a gamma camera having the function of identifying a radioactive source, namely nuclide, and a nuclide identification method, belonging to the technical field of detection of nuclear radiation; the gamma camera comprises a probe unit, a signal processing unit, a data acquisition unit and a data processing and displaying unit which are connected in sequence; the probe unit comprises a pinhole collimator, a main detector, an anti-coincidence detector and a shielding cover; the shielding cover is a cover body with a front opening; the cover body is defined by side walls at four surfaces and a side the rear side; a containing cavity for containing the main detector and the anti-coincidence detector is in the shielding cover; the pinhole collimator is arranged at the front end of the shielding cover; certain distances exist between the pinhole collimator and the main detector and between the pinhole collimator and the anti-coincidence detector; the anti-coincidence detector surrounds the four surfaces and rear side of the main detector; the main detector comprises a scintillant array and a position sensitive photomultiplier; the position sensitive photomultiplier is arranged on the rear surface of the scintillant array; and the pinhole collimator, the scintillant array and the position sensitive photomultiplier are coaxially arranged. The gamma camera disclosed by the invention is convenient to use and high in accuracy and is applied to identifying nuclide.
Description
Technical field
The invention belongs to nuclear radiation detection technical field, relating to a kind of gamma camera for carrying out radioactive source nuclide identification and radioactive source nuclide identification method, especially relating to a kind of gamma camera based on hypersorption judgment mechanism radioactive source nuclide identification and utilizing this camera to carry out the method for nuclide identification.
Background technology
Radio nuclide source terms investigation is requisite basic work in Nuclear installation decommissioning project, and its objective is quantity, kind and the space distribution of determining radioactive nuclide in place, the formulation for retired scheme provides reference and foundation.In the fields such as environment nuclear radiation monitoring, Nuclear Accident Emergency and core anti-terrorism, also need nucleic kind and the position distribution of determining radiomaterial fast.γ camera (gamma camera) is a kind of gamma (γ) ray imaging device, it can quick obtaining gamma emitter locus distribution, therefore play an important role in fields such as elimination of nuclear facilities decontamination, environment nuclear radiation monitoring and Nuclear Accident Emergency.The old process of radio nuclide source terms investigation is generally the overall space distribution first being obtained radioactive contamination material in place by gamma camera, the more concrete nucleic kind comprised by gamma (γ) spectrometer determination pollutant.But the method but cannot obtain the position distribution situation of concrete a certain nucleic.If gamma camera can realize gamma-rays imaging and nuclide identification function simultaneously, gamma camera so only need be utilized just can to know the kind of radioactive nuclide and the space distribution of each nucleic in place exactly; Radio nuclide source terms fact-finding process will become more simple, quick, and the source item data obtained also will be more accurate, complete.Therefore, in order to realize efficient radio nuclide source terms survey objective, need to possess the gamma camera that accurately can identify nucleic function.
At present, most of gamma camera all can only obtain the two-dimensional intensity distribution information of gamma ray radiator as CARTOGAM, GammaVisor and GammaCam etc., does not have nuclide identification function.2003, RMD company of the U.S. invented one and has been called " DataCube " data processing method, and is applied in RadCam2000TM gamma camera.Its basic thought gamma-ray positional information and energy information is combined store, and by selected " energy window ", can show the position distribution of specific species; Then can show the gamma spectrum of selection area by selecting " position window ".The gamma camera of the RadScan of Britain and China Atomic Energy Science Research Institute's development is also on the basis obtaining gamma spectrum, select to obtain the location distribution information of different nucleic by " energy window ".The gamma camera Medipix2 of new generation of French CAE with the CANBERRA company cooperation research and development of report in 2013 screens the signal magnitude that gamma-rays produces at detector by means of only the different threshold value of setting, realizes simple nuclide identification function thus.Generally, the current gamma camera with nuclide identification function is inherently utilize single detector measurement to obtain gamma-ray energy, then realizes nuclide identification by the setting of energy window.
But, because the interaction of gamma-rays and scintillation crystal comprises photoelectric effect, Compton scattering and pair effect three kinds possibility process.For single gamma-rays, if to there is Compton scattering or pair effect, the energy that the energy that so gamma-rays deposits in detector will not be gamma-rays itself.Be reflected on gamma spectrum, then show as in power spectrum and not only comprise full energy peak, also there is level ground, Compton and escape peak.For the place that there is mixing γ source, the gamma-ray full energy peak that energy is lower necessarily overlaps with the level ground, Compton of energetic gamma rays.Therefore, choose by setting " energy window " the Compton scattering background inevitably comprising energetic gamma rays when low-energyγ-ray carries out position display, the position distribution in this case obtained is not just the actual position distribution of selected nucleic.That is, the method chosen by energy window merely can not carry out nuclide identification effectively.Therefore, a kind of gamma camera and the nuclide identification method that fast can carry out radioactive source nuclide identification is accurately needed badly.
Summary of the invention
Technical matters to be solved by this invention overcomes the low and shortcoming of ease of use difference of accuracy rate when existing gamma camera and nuclide identification method thereof carry out nuclide identification, provides a kind of gamma camera and the nuclide identification method with radioactive source nuclide identification function.
The technical solution adopted for the present invention to solve the technical problems is: the gamma camera with radioactive source nuclide identification function, comprise the contact unit be connected successively, signal processing unit, data acquisition unit and data processing and display unit, described contact unit comprises pinhole collimator, main detector, anticoincidence detector and radome, described radome is that the sidewall of four sides and rear side is around forming the cover body with front openings, for the front end of the cavity volume radome for placing main detector and anticoincidence detector is provided with pinhole collimator in radome, the gamma ray of radioactive source is made only to enter in cavity volume by pinhole collimator, pinhole collimator and main detector, anticoincidence detector is separated with certain distance, described anticoincidence detector is centered around four sides and the rear side of main detector, described main detector comprises scintillator arrays and position sensitive photo-multiplier tube, position sensitive photo-multiplier tube is arranged on the rear surface of scintillator arrays, pinhole collimator and scintillator arrays and position sensitive photo-multiplier tube are coaxially arranged, to make light beam directly all be incided on scintillator arrays by pinhole collimator,
Signal processing unit comprises the pre-amplification circuit, gain adjusting circuit, A/D sample circuit and the microprocessor that connect successively, for amplifying the output signal of main detector and anticoincidence detector, filtering be shaped and A/D conversion process, and by process after signal transmission to data acquisition unit;
Data acquisition unit is used for the signal that Received signal strength processing unit transmits, and basis signal calculates and stores positional information and the energy information of the gamma ray of radioactive source, and by this information transmission to data processing unit, basis signal has the situation of output signal to mark and screen to main detector and anticoincidence detector simultaneously simultaneously, and the result of mark and screening is passed to data processing unit;
Data processing and display unit read positional information and the energy information of data acquisition unit transmission, and utilize the result of mark and screening to judge whether the gamma ray of radioactive source hypersorption occurs, and carry out specific species imaging.
Concrete, the probing medium of described anticoincidence detector is BGO crystal.
Concrete, described scintillator arrays is NaI or CsI or LaBr3 or LaCl3 scintillator arrays.
Further, silicone grease is coated with between described scintillator arrays and position sensitive photo-multiplier tube.
Concrete, described scintillator arrays is total area 50mm × 50mm, and cell cross-section is of a size of the bright volume array of CsI flicker of 1mm, and the model of described position sensitive photo-multiplier tube is Hamamastu R2486-02.
The present invention solves another technical scheme that its technical matters adopts:
Nuclide identification method, is characterized in that, comprises the following steps:
The first step. utilize the above-mentioned gamma camera with radioactive source nuclide identification function to obtain four tunnel output signals of main detector, and a road output signal of anticoincidence detector;
Second step. five road signals are processed;
3rd step. based on the signal after second step process, calculate, obtain position and the energy results of the gamma ray of radioactive source, and event memory, judge whether the output signal of position main detector and the output signal of anticoincidence detector are occur simultaneously simultaneously, the situation of output signal is marked and screened;
4th step. read position and the energy results of the gamma ray of radioactive source, and utilize the output signal situation of mark and screening to judge whether the gamma ray of radioactive source hypersorption occurs, and carry out specific species imaging.
Concrete, second step be specially five road signals are amplified, filtering is shaped and A/D conversion, and produces by FPGA the sample frequency that clock reference controls A-D converter ADC.
Further, before Dui five road signal amplifies in second step, need to be processed five road signals by phase electric eliminating road, pole-zero, then five road signals are passed through slide rheostat dividing potential drop, carry out signal amplification.
Concrete, in the 3rd step, need after result filtering after obtaining the position of the gamma ray of radioactive source and energy results, carry out pulse shaping successively, baseline estimations, accumulation sentence abandon, amplitude extract after event memory.
The invention has the beneficial effects as follows: in routine based on the gamma ray position measuring system basis of scintillation crystal array-PSPMT, by arranging one group of peripheral detector, the example that scintillation crystal array occurs for hypersorption or Compton scattering is differentiated; Utilize anticoincidence technique to screen the example that hypersorption occurs on host crystal, the gamma energy that measurement is obtained is corresponding with its actual energy.The measuring position of each gamma ray obtained by gamma detector and measurement energy (i.e. the total size of X, Y-coordinate and output signal) are carried out storing so that carry out data processing as a data group, finally realizes the function shown respectively according to the position distribution of gamma energy to different nucleic.The method directly can obtain the location distribution information of various specific radioactive nuclide when can make to utilize γ camera to measure, easy to use, accuracy rate is high.The present invention is applicable to carry out the operation of identification nucleic.
Accompanying drawing explanation
Fig. 1 is the structured flowchart of gamma camera of the present invention;
Fig. 2 is the structural representation of the contact unit of gamma camera of the present invention;
Fig. 3 is the schematic flow sheet of signal processing unit and data acquisition unit in the present invention;
Wherein, 1 is pinhole collimator, and 2 is scintillator arrays, and 3 is position sensitive photo-multiplier tube, and 4 is anticoincidence detector, and 5 is radome.
Embodiment
Below in conjunction with drawings and Examples, describe technical scheme of the present invention in detail.
As shown in Figure 1, the gamma camera with radioactive source nuclide identification function of the present invention, comprises contact unit, signal processing unit, data acquisition unit and the data processing and display unit that are connected successively.
As shown in Figure 2, described contact unit comprises pinhole collimator 1, main detector, anticoincidence detector 4 and radome 5, described radome 5 is for shielding visible ray, its sidewall being specially four sides and rear side is up and down around forming the cover body with front openings, it is the cavity volume for placing main detector and anticoincidence detector 4 in radome 5, the front end of radome is provided with pinhole collimator, the gamma ray of radioactive source is only to enter in cavity volume by the pinhole collimator of front side, pinhole collimator 1 and main detector, anticoincidence detector 4 is separated with certain distance, to detect the gamma ray after by described collimating apparatus transmission.Described anticoincidence detector 4 is centered around four sides and the rear side up and down of main detector, and consider based on detection efficiency and detection sensitivity, its probing medium elects BGO crystal as, adopts photomultiplier transit light to collect the passage of scintillation light that gamma-rays produces on BGO; Main detector comprises scintillator arrays 2 and position sensitive photo-multiplier tube 3, and scintillator arrays 2 is NaI or CsI or LaBr3 or LaCl3 scintillator arrays.Position sensitive photo-multiplier tube 3 is arranged on the rear surface of scintillator arrays 2, position sensitive photo-multiplier tube and scintillator arrays 2 optically-coupled are with the visible ray receiving scintillator arrays 2 and send after absorbing gamma energy and described visible ray is converted to electric signal, specifically can be coated with silicone grease between and be fixed; Pinhole collimator and scintillator arrays 2 and position sensitive photo-multiplier tube 3 are coaxially arranged, to make light beam directly all be incided on scintillator arrays 2 by pinhole collimator.
Signal processing unit comprises the pre-amplification circuit, gain adjusting circuit and the A/D sample circuit that connect successively, signal processing unit is connected with main detector, anticoincidence detector 4 and data acquisition unit respectively, for amplifying the output signal of main detector and anticoincidence detector 4, filtering be shaped and A/D conversion process, and by process after signal transmission to data acquisition unit;
Data acquisition unit is used for the signal that Received signal strength processing unit transmits, and basis signal calculates and stores positional information and the energy information of the gamma ray of radioactive source, and by this information transmission to data processing unit, basis signal has the situation of output signal to mark and screen to main detector and anticoincidence detector 4 simultaneously simultaneously, and the result of mark and screening is passed to data processing unit;
Data processing and display unit read positional information and the energy information of data acquisition unit transmission, and utilize the result of mark and screening to judge whether the gamma ray of radioactive source hypersorption occurs, and carry out specific species imaging, finally complete the display of gamma ray two dimensional image and the display of power spectrum.This unit specifically can be made up of software, display and processor.
In order to identify radioactive source nucleic, its method comprises: utilize the above-mentioned gamma camera with radioactive source nuclide identification function to obtain four tunnel output signal A, B, C, D of main detector, and a road output signal T of anticoincidence detector; Five road signals are amplified, filtering is shaped and A/D changes, and produce by FPGA the sample frequency that clock reference controls A-D converter ADC; Based on the signal after aforementioned processing, calculate, obtain position and the energy results of the gamma ray of radioactive source, and event memory, judge whether the output signal of position main detector and the output signal of anticoincidence detector are occur simultaneously simultaneously, the situation of output signal is marked and screened; Read position and the energy results of the gamma ray of radioactive source, and utilize the output signal situation of mark and screening to judge whether the gamma ray of radioactive source hypersorption occurs, and carry out specific species imaging.
Embodiment
The gamma camera with radioactive source nuclide identification function in this example comprises following part, and its method refers to each several part and describes:
(1) contact unit
Set up and pop one's head in based on the gamma camera of " pinhole collimator---scintillator arrays---position sensitive photo-multiplier tube " structure.Adopt total area 50mm × 50mm, the CsI scintillator arrays that cell cross-section is of a size of 1mm coordinates HamamastuR2486-02 position sensitive photo-multiplier tube as gamma-rays position measuring system.Collimating apparatus adopts tungalloy to form, and meets total visual field corresponding to the sensitive area of scintillator and reach 30 ° × 30 °, outside pin hole during pinhole size design
60the transmitance of Co 1.33MeV gamma ray is less than 0.1%.Gamma-rays is beaten after on scintillator arrays by after pinhole collimator, will produce signal on four of a HamamastuR2486-02 position sensitive photo-multiplier tube output terminal.The amplitude output signal that can be recorded four output terminals by postorder unit is respectively A, B, C and D, then can be determined by formula X=A/ (A+B), Y=C/ (C+D) the two-dimensional coordinate of gamma-ray measurement position, gamma-ray energy is calculated by formula E=k* (A+B+C+D).When there being a large amount of gamma-rays incident, measure by position sensitive photo-multiplier tube the two-dimensional space distribution that the position distribution of gamma-rays on scintillator just instead can release gamma ray radiator.
(2) signal processing unit
Comprise pre-amplification circuit, gain adjusting circuit, A/D sample circuit and microprocessor, the work mainly completed is the gamma-rays that radioactive source radiates, and it is converted to electric signal, again through rough handlings such as amplification, filtering shaping, A/D conversions, the gamma-rays obtaining catching beats accurate location information on the crystal of contact unit and energy information, meets at data acquisition unit and carries out specific Data acquisition and transmit.
The probe portion of gamma camera comprises main detector and the anticoincidence detector as peripheral detector.γ camera based on HamamastuR2486-02 have A, B, C, D tetra-tunnel output signal, peripheral detector have one tunnel output signal T.The prime amplifier of a development Five-channel, then for a set of filtering wave-shaping circuit of prime amplifier output signal design.The output signal of wave-shaping circuit carries out digitizing by A/D conversion chip, produces clock reference to control the sample frequency of A-D converter ADC by FPGA (Field-Programmable Gate Array, field programmable gate array).
(3) data acquisition unit
Data acquisition unit mainly completes gamma-ray position calculation, energy balane and result and stores, judge whether position sensitive photo-multiplier tube output signal and peripheral anticoincidence detector output signal are occur simultaneously simultaneously, follow-up γ imaging software system the situation of output signal marked and screened, so that can be distinguished to the gamma-rays that hypersorption or Compton scattering occur.It is crucial for carry out stores synchronized to gamma-ray positional information and energy information, (namely each gamma-ray X, Y-coordinate want corresponding with ENERGY E).
To the signal processing of two detectors and data acquisition as shown in Figure 3.
The signal period that front-end detector exports is longer, what forward position rose is very fast, then but very slow along the speed dropping to baseline, be not suitable for the follow-up analysis requirement to input signal like this, need the narrowed width of pulse through phase electric eliminating road, pole-zero, so that the situation of high count rate can be adapted to, reduce the fluctuation of heap sum baseline simultaneously as far as possible;
Through A, the B on phase electric eliminating road, pole-zero, C, D, T five road signal, carries out dividing potential drop by a slide rheostat, regulates slide rheostat the amplitude of input pulse to be transferred to the scope of needs, thus carries out signal amplification.
The five road signals amplified by signal, due to the impact by environment temperature, the process ratio measured is easier to produce peak drift, at this time just can by regulating enlargement factor or the high pressure of detector crystal improves this situation, usually can only realize coarse adjustment to the adjustment of the high pressure of detector crystal, want to realize accurate adjustment still by using digital regulation resistance or DAC to realize minute adjustment thus alleviating peak drift object.Pending pulse signal is input to the reference edge of DAC, the input end of digital signal will use as control port, and original analog output end will still as signal output part.By the digital signal of control inputs, can the enlargement factor of simulating signal of regulation output, if the digital quantity of input is constant, then magnification ratio is certain; If desired magnification ratio is changed, only need by changing the input quantity of digital end in microprocessor program.
Through the signal that signal gain regulates, import five road A/D modular converter samplings into, obtain digital signal.Between A/D conversion and latches data, load data fifo buffering, reach the interference slowing down different units clock difference and cause.Signal after latches data, is divided into A1, B1, C1, D1 data, and A1, B1, C1, D1, T1 data two groups of data bufferings are in FIFO.First group of data A1, B1, C1, D1 read in SOPC SOC (system on a chip), after being sued for peace by formula E=A+B+C+D by energy, enter digital filtering module and carry out simple filtering process, reject " burr " interference, afterwards and be advanced into that 4 modules are pulse shaping module respectively, baseline estimations module, pile up to sentence and abandon module, amplitude extraction module.First be transferred to shaping module, this module comprises one and is shaped soon and is shaped slowly, and fast shaping mainly obtains the time interval between pulse, and for piling up identification, fast shaping obtains fast channel counts rate for correction of the count rate simultaneously.And be shaped slowly compared with being shaped soon, there is longer rising time and wider flat-top, the amplitude that mainly realizes is extracted and baseline estimations, actual pulse height is the difference between the amplitude that extracts of amplitude extraction module and baseline estimations value, therefore two modules are exported with the adjustment realizing amplitude, finally realize peak-seeking function.Other first group of data A1, B1, C1, D1 read in position computation module, and the IP kernel calling FPGA carries out position calculation according to formula X=A/ (A+B), Y=C/ (C+D), and by result cache.
Second group of data A1, B1, C1, D1, T1, read in real time record unit, this unit mainly comprises data delay, pulse capture, impulse sampling point length records function.When pulse signal voltage is greater than setting starting potential, the current data of A1, B1, C1, D1, T1 respectively read in buffer zone, and other data enter latch delay, then stop starting when being less than setting starting potential.The data of reading in buffer zone are carried out pulse capture, now impulse meter and are started counting, until receive stop signal, and now recording gauge numerical value respectively.Now count value is compared, if comparison domain is identical, then will captures A1, B1, C1, D1 and compare with T1 respectively, record comparative result, so that later stage mapping.
Data buffer storage after FPGA process is in SDRAM chip, and the high-speed transfer by driving usb circuit to carry out data, thus complete the Acquire and process of data.
(4) data processing and display unit
Gamma-ray position, energy information transfer to computing machine by USB interface after FPGA process.γ imaging software in computing machine reads gamma-ray positional information and energy information by USB interface, and whether the mark utilizing data acquisition system (DAS) to set, to gamma-rays, hypersorption occurs judges.Then according to above-mentioned information, imaging display is carried out to specific species, finally complete the display of gamma-rays two dimensional image and the display of power spectrum.
Claims (9)
1. there is the gamma camera of radioactive source nuclide identification function, it is characterized in that, comprise contact unit, signal processing unit, data acquisition unit and the data processing and display unit that are connected successively;
Described contact unit comprises pinhole collimator (1), main detector, anticoincidence detector (4) and radome (5), described radome (5) is that the sidewall of four sides and rear side is around forming the cover body with front openings, it is the cavity volume for placing main detector and anticoincidence detector (4) in radome (5), the front end of radome is provided with pinhole collimator, the gamma ray of radioactive source is made only to enter in cavity volume by pinhole collimator (1), pinhole collimator (1) and main detector, anticoincidence detector (4) is separated with certain distance, described anticoincidence detector (4) is centered around four sides and the rear side of main detector, described main detector comprises scintillator arrays (2) and position sensitive photo-multiplier tube (3), position sensitive photo-multiplier tube (3) is arranged on the rear surface of scintillator arrays (2), pinhole collimator and scintillator arrays (2) and position sensitive photo-multiplier tube (3) are coaxially arranged, to make light beam directly all incide on scintillator arrays (2) by pinhole collimator,
Signal processing unit comprises the pre-amplification circuit, gain adjusting circuit, A/D sample circuit and the microprocessor that connect successively, for amplifying the output signal of main detector and anticoincidence detector (4), filtering be shaped and A/D conversion process, and by process after signal transmission to data acquisition unit;
Data acquisition unit is used for the signal that Received signal strength processing unit transmits, and basis signal calculates and stores positional information and the energy information of the gamma ray of radioactive source, and by this information transmission to data processing unit, basis signal has the situation of output signal to mark and screen to main detector and anticoincidence detector (4) simultaneously simultaneously, and the result of mark and screening is passed to data processing unit;
Data processing and display unit read positional information and the energy information of data acquisition unit transmission, and utilize the result of mark and screening to judge whether the gamma ray of radioactive source hypersorption occurs, and carry out specific species imaging.
2. have the gamma camera of radioactive source nuclide identification function as claimed in claim 1, it is characterized in that, the probing medium of described anticoincidence detector is BGO crystal.
3. have the gamma camera of radioactive source nuclide identification function as claimed in claim 1, it is characterized in that, described scintillator arrays (2) is NaI or CsI or LaBr3 or LaCl3 scintillator arrays.
4. there is the gamma camera of radioactive source nuclide identification function as claimed in claim 3, it is characterized in that, between described scintillator arrays (2) and position sensitive photo-multiplier tube (3), be coated with silicone grease.
5. there is the gamma camera of radioactive source nuclide identification function as claimed in claim 1, it is characterized in that, described scintillator arrays (2) is total area 50mm × 50mm, cell cross-section is of a size of the bright volume array of CsI flicker of 1mm, and the model of described position sensitive photo-multiplier tube is Hamamastu R2486-02.
6. nuclide identification method, is characterized in that, comprises the following steps:
The first step. utilize the gamma camera with radioactive source nuclide identification function as described in claim 1 to 5 any one to obtain four tunnel output signal A, B, C, D of main detector, and a road output signal T of anticoincidence detector;
Second step. five road signals are processed;
3rd step. based on the signal after second step process, calculate, obtain position and the energy results of the gamma ray of radioactive source, and event memory, judge whether the output signal of position main detector and the output signal of anticoincidence detector are occur simultaneously simultaneously, the situation of output signal is marked and screened;
4th step. read position and the energy results of the gamma ray of radioactive source, and utilize the output signal situation of mark and screening to judge whether the gamma ray of radioactive source hypersorption occurs, and carry out specific species imaging.
7. nuclide identification method as claimed in claim 6, is characterized in that, second step be specially five road signals are amplified, filtering is shaped and A/D conversion, and produces by FPGA the sample frequency that clock reference controls A-D converter ADC.
8. nuclide identification method as claimed in claim 7, it is characterized in that, before Dui five road signal amplifies in second step, need to be processed five road signals by phase electric eliminating road, pole-zero, then five road signals are passed through slide rheostat dividing potential drop, carry out signal amplification.
9. nuclide identification method as claimed in claim 6, it is characterized in that, in 3rd step, need after result filtering after obtaining the position of the gamma ray of radioactive source and energy results, carry out pulse shaping successively, baseline estimations, accumulation sentence abandon, amplitude extract after event memory.
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Publication number | Priority date | Publication date | Assignee | Title |
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-
2014
- 2014-12-09 CN CN201410748880.0A patent/CN104360376A/en active Pending
Non-Patent Citations (7)
Title |
---|
丁洪林: "《核辐射探测器》", 30 April 2010 * |
张廷逵等: "锗酸秘晶体作低本底液闪反符合屏蔽的尝试", 《核电子学与探测技术》 * |
张怀强等: "数字核谱仪系统中脉冲堆积识别方法的研究", 《东华理工大学学报( 自然科学版)》 * |
杨守礼等: "《液体闪烁测量技术的进展与应用》", 31 October 1987 * |
汲长松: "《核辐射探测器及其实验技术手册》", 31 October 1990 * |
潘松等: "《EDA技术使用教程》", 31 October 2002 * |
陈非凡: "《仪器设计技术基础》", 31 August 2007 * |
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