CN103558626A - Gamma ray detector and gamma ray processing method - Google Patents

Gamma ray detector and gamma ray processing method Download PDF

Info

Publication number
CN103558626A
CN103558626A CN201310567701.9A CN201310567701A CN103558626A CN 103558626 A CN103558626 A CN 103558626A CN 201310567701 A CN201310567701 A CN 201310567701A CN 103558626 A CN103558626 A CN 103558626A
Authority
CN
China
Prior art keywords
pulse
gamma
photoelectric commutator
scintillation crystal
ray
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Granted
Application number
CN201310567701.9A
Other languages
Chinese (zh)
Other versions
CN103558626B (en
Inventor
伍军
郭兴维
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
BEIJING ARENA CENTURY PETROLEUM TECHNOLOGY Co Ltd
Original Assignee
BEIJING ARENA CENTURY PETROLEUM TECHNOLOGY Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by BEIJING ARENA CENTURY PETROLEUM TECHNOLOGY Co Ltd filed Critical BEIJING ARENA CENTURY PETROLEUM TECHNOLOGY Co Ltd
Priority to CN201310567701.9A priority Critical patent/CN103558626B/en
Publication of CN103558626A publication Critical patent/CN103558626A/en
Priority to PCT/CN2014/077174 priority patent/WO2015070578A1/en
Application granted granted Critical
Publication of CN103558626B publication Critical patent/CN103558626B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Classifications

    • GPHYSICS
    • G01MEASURING; TESTING
    • G01TMEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T1/00Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
    • G01T1/16Measuring radiation intensity
    • G01T1/20Measuring radiation intensity with scintillation detectors
    • G01T1/2006Measuring radiation intensity with scintillation detectors using a combination of a scintillator and photodetector which measures the means radiation intensity

Landscapes

  • Physics & Mathematics (AREA)
  • Health & Medical Sciences (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

The invention discloses a gamma ray detector and a gamma ray processing method. The gamma ray detector comprises n scintillation crystals with the numbers from A1 to An, a first photoelectric converter, a second photoelectric converter and a processing circuit. The n scintillation crystals are arranged side by side, a scintillation crystal Ai and a scintillation crystal Ai+1 are arranged in an end-to-end mode; the first photoelectric converter is arranged at the first end of a scintillation crystal A1; the second photoelectric converter is arranged at the first end of a scintillation crystal An; the processing circuit is connected with the first photoelectric converter and the second photoelectric converter and is used for receiving a first pulse and a second pulse, and the incidence position of gamma rays is computed and/or the energy of the gamma rays is corrected according to the first pulse and the second pulse. According to the gamma ray detector and the gamma ray processing method, the problem that in the existing gamma ray detecting technology, the axial resolution ratio is low, and gamma ray energy detecting accuracy is low is solved, and accordingly the purpose that the measuring accuracy of the gamma ray detector is improved is achieved.

Description

The disposal route of gamma-ray detector and gamma ray
Technical field
The present invention relates to Detection Techniques field, in particular to the disposal route of a kind of gamma-ray detector and gamma ray.
Background technology
At geological exploration field, different stratum, the content of radioelement is different with kind, and the intensity of utilizing gamma-ray detector to survey gamma ray in stratum can be distinguished stratum and definite stratum element.Fig. 1 is the structural representation of gamma-ray detector conventional in prior art, as shown in Figure 1, current gamma-ray detector is generally comprised of a scintillation crystal A and the photomultiplier R that is arranged on this scintillation crystal A one end, when having gamma ray to inject scintillation crystal, having passage of scintillation light produces, by photomultiplier, collect photoelectron, after amplifying at double, at output terminal, produce pulse current, in Fig. 1, label γ 1, γ 2, γ 3 and γ 4 all represent gamma ray, and Eh represents zone thickness.By certain method, electric impulse signal is processed and gathered, obtain the information relevant to stratum and stratum element.Uncertainty due to gamma energy, and the randomness of time of incidence and direction, gamma-ray detector of the prior art can only carry out the processing of stratum and stratum element information in the scope that is greater than scintillation crystal length, cannot differentiate gamma ray is from which position of crystal to inject, there is the drawback that stratigraphic resolution is lower, in addition, due to the absorption of crystal to the passage of scintillation light of rays excite itself, cause the accuracy of energy measurement to decline.
For axial resolution in original gamma ray detection technology and the low problem of energy measurement accuracy, effective solution is not yet proposed at present.
Summary of the invention
Fundamental purpose of the present invention is to provide the disposal route of a kind of gamma-ray detector and gamma ray, to solve axial resolution and the low problem of energy measurement accuracy in existing gamma ray detection technology.
To achieve these goals, according to an aspect of the present invention, provide a kind of gamma-ray detector, having comprised: be numbered A 1to A nn scintillation crystal, wherein, n scintillation crystal is set up in parallel, and scintillation crystal A iwith scintillation crystal A i+1end-to-end setting, n is more than 2 natural number, i gets 1 successively to n-1; The first photoelectric commutator, is arranged on scintillation crystal A 1first end, wherein, scintillation crystal A 1first end be away from scintillation crystal A 2one end; The second photoelectric commutator, is arranged on scintillation crystal A nfirst end, wherein, scintillation crystal A nfirst end be away from scintillation crystal A n-1one end; And treatment circuit, all be connected with the second photoelectric commutator with the first photoelectric commutator, be used for receiving the first pulse and the second pulse, and calculate the incoming position of gamma ray and/or the energy of correction gamma ray according to the first pulse and the second pulse, wherein, the first pulse is the pulse of the first photoelectric commutator output, and the second pulse is the pulse of the second photoelectric commutator output.
Further, gamma-ray detector also comprises: light conductor, the number of light conductor is a plurality of, wherein, light conductor is arranged on one of at least position in primary importance, the second place and the 3rd position, primary importance is the position between every two adjacent scintillation crystals, and the second place is scintillation crystal A 1first end, the 3rd position is scintillation crystal A nfirst end.
Further, gamma-ray detector also comprises: housing, wherein, n scintillation crystal, the first photoelectric commutator, the second photoelectric commutator and a plurality of light conductor are all arranged in housing.
Further, gamma-ray detector also comprises: the first base, is arranged in housing, for carrying the first photoelectric commutator; The second base, is arranged in housing, for carrying the second photoelectric commutator; The first plug, is arranged on the first end of housing; The second plug, is arranged on the second end of housing; The first damping part, is arranged between the first plug and the first base; And second damping part, be arranged between the second plug and the second base.
Further, gamma-ray detector also comprises: shield, the number of shield is a plurality of, wherein, shield is set in one of at least circle segment place in the first circle segment, the second circle segment, the 3rd circle segment and the 4th circle segment of housing, wherein, the first circle segment is the housing parts around each light conductor, the second circle segment is the housing parts around each scintillation crystal, the 3rd circle segment is the housing parts around the first photoelectric commutator, and the 4th circle segment is the housing parts around the second photoelectric commutator.
Further, in n scintillation crystal, the crystalline material of any two scintillation crystals is identical or different.
Further, in a plurality of light conductors, the optical transmittance of any two light conductors is identical or different.
Further, the first pulse and the second pulse are electric pulse, and treatment circuit comprises: amplifier, is all connected with the second photoelectric commutator with the first photoelectric commutator, for the first pulse and the second pulse are carried out to Hyblid Buffer Amplifier and shaping; Analog to digital converter, is connected with amplifier, for gathering pulse height or the area of the first pulse and the second pulse, and the output digital signal corresponding with pulse height or area; And processor, be connected with analog to digital converter, for calculating the difference value of the digital signal that represents the first pulse and the second pulse, and according to difference value and scintillation crystal, the attenuation coefficient of passage of scintillation light is calculated to the incoming position of gamma ray and the energy after correction.
Further, the first pulse and the second pulse are electric pulse, and treatment circuit comprises: amplifier, is all connected with the second photoelectric commutator with the first photoelectric commutator, for the first pulse and the second pulse are carried out to Hyblid Buffer Amplifier and shaping; The first logical-arithmetic unit, is connected with amplifier, for obtaining the difference signal of the first pulse and the second pulse; The second logical-arithmetic unit, is connected with the first logical-arithmetic unit, for the attenuation coefficient of passage of scintillation light being calculated to the incoming position of gamma ray and/or the energy of the gamma ray after correction according to difference signal and scintillation crystal.
To achieve these goals, according to a further aspect in the invention, a kind of disposal route of gamma ray is provided, be applied to target gamma-ray detector, the two ends of target gamma-ray detector all have photoelectric commutator, disposal route comprises: receive the first pulse and the second pulse, wherein, the first pulse is the pulse of the first photoelectric commutator output, the second pulse is the pulse of the second photoelectric commutator output, the first photoelectric commutator is the photoelectric commutator that is arranged on target gamma-ray detector first end, the second photoelectric commutator is the photoelectric commutator that is arranged on target gamma-ray detector the second end, and calculate the incoming position of gamma ray and/or the energy of correction gamma ray according to the first pulse and the second pulse.
Further, target gamma-ray detector also comprises scintillation crystal, the first pulse and the second pulse are electric pulse, and the energy that calculates the incoming position of gamma ray and/or proofread and correct gamma ray according to the first pulse and the second pulse comprises: determine range value or area value that the first pulse and the second pulse are corresponding; Determine range value or area value and the range value of the second pulse or the difference value of area value of the first pulse; And the attenuation coefficient of passage of scintillation light is calculated to the energy of incoming position and/or correction gamma ray according to difference value and scintillation crystal.
Further, target gamma-ray detector also comprises scintillation crystal, the first pulse and the second pulse are electric pulse, and the energy that calculates the incoming position of gamma ray and/or proofread and correct gamma ray according to the first pulse and the second pulse comprises: determine range signal or area of signal that the first pulse and the second pulse are corresponding; Determine range signal or area of signal and the range signal of the second pulse or the difference signal of area of signal of the first pulse; And according to difference signal and scintillation crystal, the attenuation coefficient of passage of scintillation light is directly exported to the incoming position of gamma ray and/or the energy of the gamma ray after correction.
Further, the first pulse and the second pulse are electric pulse, according to the energy of the first pulse and the second impulse correction gamma ray, comprise: determine range value or area value that the first pulse and the second pulse are corresponding; Determine range value or area value and the range value of the second pulse or the geometrical mean of area value or arithmetic mean or the weighted mean value of the first pulse; And with range value or area value and the range value of the second pulse or the geometrical mean of area value or arithmetic mean value or the weighted mean value of the first pulse, replace the range value of the first pulse and/or the second pulse or area value as the energy measure of gamma ray.
Further, after according to the energy of the first pulse and the second impulse correction gamma ray, disposal route also comprises: the gamma ray after correcting energy is applied to destination apparatus, and wherein, destination apparatus is for measuring the device of counting rate, energy window or the power spectrum of gamma ray.
The present invention adopts the gamma-ray detector with following structure: be numbered A 1to A nn scintillation crystal, wherein, n scintillation crystal is set up in parallel, and scintillation crystal A iwith scintillation crystal A i+1end-to-end setting, n is more than 2 natural number, i gets 1 successively to n-1; The first photoelectric commutator, is arranged on scintillation crystal A 1first end, wherein, scintillation crystal A 1first end be away from scintillation crystal A 2one end; The second photoelectric commutator, is arranged on scintillation crystal A nfirst end, wherein, scintillation crystal A nfirst end be away from scintillation crystal A n-1one end; And treatment circuit, all be connected with the second photoelectric commutator with the first photoelectric commutator, be used for receiving the first pulse and the second pulse, and calculate the incoming position of gamma ray and/or the energy of correction gamma ray according to the first pulse and the second pulse, wherein, the first pulse is the pulse of the first photoelectric commutator output, and the second pulse is the pulse of the second photoelectric commutator output.By a plurality of scintillation crystals that are set up in parallel are set, and the end-to-end setting of these a plurality of scintillation crystals, and at the two ends of the scintillation crystal being set up in parallel, photoelectric commutator is set respectively, realized and can from the both sides of scintillation crystal, light signal received and be processed respectively, and then different to the passage of scintillation light energy attenuation of the different light paths of passing by according to scintillation crystal, and corresponding voltage amplitude or the area of two light signals obtaining, accurately calculate the incoming position of gamma ray and/or the energy of correction gamma ray, solved in prior art the lower and low problem of gamma energy accuracy of measurement of axial resolution, and then reached the object that improves gamma-ray detector measuring accuracy.
Accompanying drawing explanation
The accompanying drawing that forms the application's a part is used to provide a further understanding of the present invention, and schematic description and description of the present invention is used for explaining the present invention, does not form inappropriate limitation of the present invention.In the accompanying drawings:
Fig. 1 is according to the structural representation of the gamma-ray detector of correlation technique;
Fig. 2 is according to the sectional view of the gamma-ray detector of the embodiment of the present invention;
Fig. 3 is the sectional view of gamma-ray detector according to the preferred embodiment of the invention; And
Fig. 4 is according to the process flow figure of the gamma ray of the embodiment of the present invention.
Embodiment
It should be noted that, in the situation that not conflicting, embodiment and the feature in embodiment in the application can combine mutually.Describe below with reference to the accompanying drawings and in conjunction with the embodiments the present invention in detail.
The embodiment of the present invention provides a kind of gamma-ray detector, below gamma-ray detector that the embodiment of the present invention is provided be specifically introduced:
Fig. 2 is according to the sectional view of the gamma-ray detector of the embodiment of the present invention, as shown in Figure 2, the gamma-ray detector of the embodiment of the present invention mainly comprises a plurality of scintillation crystals, the first photoelectric commutator 21, the second photoelectric commutator 22 and treatment circuit (not shown), wherein:
A plurality of scintillation crystals be numbered A 1to A n, n scintillation crystal is set up in parallel, and scintillation crystal A iwith scintillation crystal A i+1end-to-end setting, i gets 1 successively to n-1,, n scintillation crystal connected and formed strip crystal assembly in end-to-end mode, the two end faces of crystal assembly is optical side window S1 and S2, n is more than 2 natural number, has schematically shown the sectional view by the formed gamma-ray detector of 3 scintillation crystals (being n=3) in Fig. 2.
The first photoelectric commutator 21 is arranged on scintillation crystal A 1first end, wherein, scintillation crystal A 1first end be away from scintillation crystal A 2one end,, the first photoelectric commutator 21 is arranged on an end of crystal assembly, for receiving from optical side window S1 the photon that gamma ray spreads out of through crystal assembly, and convert the photon receiving to electric pulse, in embodiments of the present invention, the first photoelectric commutator 21 can be photomultiplier, can be also other device that can carry out photon reception and carry out opto-electronic conversion.
The second photoelectric commutator 22 is arranged on scintillation crystal A nfirst end, wherein, scintillation crystal A nfirst end be away from scintillation crystal A n-1one end,, the second photoelectric commutator 22 is arranged on the place, other end of crystal assembly, for receiving from optical side window S2 the photon that gamma ray spreads out of through crystal assembly, and convert the photon receiving to electric pulse, in embodiments of the present invention, the second photoelectric commutator 22 can be photomultiplier equally, can be also other device that can carry out photon reception and carry out opto-electronic conversion.
Treatment circuit is all connected with the second photoelectric commutator 22 with the first photoelectric commutator 21, be used for receiving the first pulse and the second pulse, and calculate the incoming position of gamma ray and/or the energy of correction gamma ray according to the first pulse and the second pulse, wherein, the first pulse is the pulse of the first photoelectric commutator 21 outputs, and the second pulse is the pulse of the second photoelectric commutator 22 outputs.
By the gamma-ray detector of said structure, because detector has a plurality of scintillation crystals, when only injecting scintillation crystal, gamma ray just can produce passage of scintillation light, by the two ends at crystal assembly, connect two photoelectric commutators, when having gamma ray inject scintillation crystal and produce flash of light, light beam can be respectively transmission path by separately to two ends, transmit, and arrive two photoelectric commutators, because scintillation crystal is different to the energy attenuation of the passage of scintillation light of the different light paths of passing by, so when gamma ray is injected crystal, when the photon inspiring transmits the light path difference of passing by crystal assembly both ends of the surface, energy attenuation is just different, therefore, by treatment circuit to processing from the pulse signal of two photoelectric commutators, can obtain amplitude (or area) difference of two pulses, and then calculate the incoming position of gamma ray and/or the energy of correction gamma ray based on this amplitude (or area) difference, such as when ray is from crystal A1(or crystal A3) during incident, the pulse height (or area) of the photoelectric commutator output on (or right left side) both sides, left and right differs larger, when ray is during from crystal A2 incident, the pulse height (or area) of the photoelectric commutator output of the right and left differs less.
The gamma-ray detector that the embodiment of the present invention provides, by a plurality of scintillation crystals that are set up in parallel are set, and the end-to-end setting of these a plurality of scintillation crystals, and at the two ends of the scintillation crystal being set up in parallel, photoelectric commutator is set respectively, realized and from the both sides of scintillation crystal, light signal has been received and processed respectively, and then can according to from two pulse signal and the attenuation effects of scintillation crystal to the gamma ray of different light paths and energy that light signal is corresponding, accurately calculate the incoming position of gamma ray and/or the energy of correction gamma ray, existing gamma-ray detector axial resolution and the lower problem of energy resolution have been solved, , solved the low problem of gamma energy accuracy of measurement in prior art, and then reached the effect that improves gamma-ray detector measuring accuracy.
In embodiments of the present invention, in a plurality of scintillation crystals, the crystalline material of any two scintillation crystals can be identical, can be not identical yet, in embodiments of the present invention, a plurality of scintillation crystals can all adopt sodium iodide crystal, also can all adopt cesium iodide crystal, can also both comprise sodium iodide crystal, comprise again cesium iodide crystal, further, all using gamma ray incident and matter interaction and produce scintillator that passage of scintillation light is mechanism can be as the substituting of above-mentioned scintillation crystal, such as bismuth germanium oxide (BGO) crystal and lanthanum bromide (LaB3r) crystal etc.
By use the crystal of different materials in a gamma-ray detector, because the crystal of different materials has difference to the response of ray, use the detector of this structure can detect this difference, reach the effect that improves gamma-ray detector detection accuracy, improved the accommodation of gamma detector.
Particularly, the second pulse of the first pulse of the first photoelectric commutator output and the output of the second photoelectric commutator is electric pulse, treatment circuit mainly contains two kinds of structure building forms, mode one: treatment circuit mainly comprises amplifier, analog to digital converter and processor, wherein:
Amplifier is all connected with the second photoelectric commutator with the first photoelectric commutator, for the first pulse and the second pulse are cushioned, amplification and shaping;
Analog to digital converter is connected with amplifier, for gathering the voltage amplitude (or area) of the first pulse and the second pulse, and the output digital signal corresponding with pulse voltage amplitude (or area);
Processor is connected with analog to digital converter, for calculating the position corresponding with digital signal and energy, obtains the incoming position of gamma ray and the energy after correction.Particularly, be mainly the difference value of calculating the digital signal that represents the first pulse and the second pulse, then, according to difference value and scintillation crystal, the attenuation coefficient of passage of scintillation light calculated to the incoming position of gamma ray and the energy after correction, wherein, difference value is difference or ratio or logarithm value.
Mode two: treatment circuit mainly comprises amplifier, the first logical-arithmetic unit and the second logical-arithmetic unit, wherein:
Amplifier is all connected with the second photoelectric commutator with the first photoelectric commutator, for the first pulse and the second pulse are carried out to Hyblid Buffer Amplifier and shaping.
The first logical-arithmetic unit is connected with amplifier, for obtaining the difference signal of the first pulse and the second pulse, wherein, the first logical-arithmetic unit is for take circuit totalizer or subtracter or multiplier or logarithm device or differential amplifier or comparer as main logical-arithmetic unit, and difference signal is difference signal or ratio signal or logarithmic signal.
The second logical-arithmetic unit is connected with the first logical-arithmetic unit, for the attenuation coefficient of passage of scintillation light being calculated to the incoming position of gamma ray and/or the energy of the gamma ray after correction according to difference signal and scintillation crystal, wherein, the second logical-arithmetic unit can be to take multiplier or comparer or logarithm device as main logical-arithmetic unit.
Further, the gamma-ray detector that the embodiment of the present invention provides also comprises the light conductor being formed by optical material, light conductor can solely be arranged between every two adjacent scintillation crystals,, between every two adjacent scintillation crystals, be provided with a light conductor, can be solely arranged on scintillation crystal A 1first end, can solely be arranged on scintillation crystal A nfirst end, can also in above-mentioned three positions, on any two or more positions, light conductor be all set, in Fig. 2, schematic diagram has illustrated to be solely arranged between every two adjacent scintillation crystals light conductor has been set, the crystal assembly being formed by 3 scintillation crystals schematically showing in corresponding diagram 2, the quantity of light conductor is 2, and these two light conductors are expressed as B1, B2 in Fig. 2.
It should be noted that, a kind of schematic diagram just in Fig. 2 with the gamma-ray detector of light conductor, in the embodiment of the present invention, does not limit the total quantity that the total quantity of light conductor in gamma-ray detector is less than scintillation crystal, when according to actual needs, need to be at scintillation crystal A 1first end and/or scintillation crystal A nfirst end light conductor is all set, corresponding diagram 2, is at scintillation crystal A 1left end light conductor is set, and/or at scintillation crystal A 3right-hand member light conductor is set.
Wherein, the optical material that is arranged on a plurality of light conductors between every two scintillation crystals can be identical, can be not identical yet, in embodiments of the present invention, a plurality of light conductors can all adopt the optical material that optical transmittance is identical, also can all adopt the optical material that optical transmittance is not identical, can also both comprise the optical material that optical transmittance is identical, comprise again the optical material that optical transmittance is not identical.For certain concrete light conductor, both can select the completely transparent optical material that glistens, to light not decay completely, utilize scintillation crystal to realize function described in this detector to the decay of photon; Also can select flash of light to have the material of certain attenuation, thereby artificial increase decay makes amplitude (or area) difference more obvious.
As previously mentioned, when only injecting scintillation crystal, ray just can produce flash of light, and inject this light conductor, just can not produce flash of light, the acquisition precision of circuit has certain limitation, for two flashes of light in crystal A1 right-hand member and the generation of crystal A2 left end, in order to distinguish this flash of light, belong to A1's or A2's, increase light conductor and just isolate and can well differentiate.So by utilizing light conductor that every two scintillation crystals are separated, the layering that is more conducive to detector is processed.In addition, use and have the light conductor of the light-guide material of decay better to the electrical pulse amplitudes (or area) of two photoelectric conversion device outputs, to differentiate to light.
Further, the gamma-ray detector of the embodiment of the present invention also comprises housing, and a said n scintillation crystal, the first photoelectric commutator 21, the second photoelectric commutator 22 and a plurality of light conductor are all fixedly installed in housing.
By utilizing housing to be fixed above-mentioned each device, realized and kept the relative position of each device to remain unchanged, to avoid affecting because of the change of sensitive detection parts relative position in measuring process the detection accuracy of gamma ray, reached the effect that improves detector accuracy.
Fig. 3 is the sectional view of gamma-ray detector according to the preferred embodiment of the invention, as shown in Figure 3, the gamma-ray detector of the preferred embodiment is compared with the gamma-ray detector shown in Fig. 2, the two difference is, the gamma-ray detector of the preferred embodiment also comprises shield, wherein, the quantity of shield is identical from the quantity of light conductor also can be different, for the quantity of the shield situation identical with the quantity of light conductor, an all corresponding sheathed shield on the housing parts around each light conductor.In Fig. 3, schematically shown the situation that corresponding light conductor quantity is 2, the quantity of shield is 4, wherein, and shield C 1be set in light conductor B 1upper, shield C 2be set in light conductor B 2upper, shield C 3be set on the first photoelectric commutator 21 shield C 4be set on the second photoelectric commutator 22, in Fig. 3, label 10 represents to comprise the crystal assembly of scintillator and light conductor.In embodiments of the present invention, shield C isize can be greater than light conductor B isize, for this situation, shield C icenter section be arranged on light conductor B iupper, shield C itwo end portions respectively correspondence be arranged on scintillation crystal A iwith scintillation crystal A i-1on.
Further, shield can also be set in the other parts place of housing, suppose that on housing, the housing parts around each light conductor is the first circle segment, housing parts around each scintillation crystal on housing is the second circle segment, housing parts around the first photoelectric commutator on housing is the 3rd circle segment, housing parts around the second photoelectric commutator on housing is the 4th circle segment, and shield can be set in one of at least circle segment place in the first circle segment, the second circle segment, the 3rd circle segment and the 4th circle segment of housing.
In actual measurement process, except along stratum horizontal direction is injected the gamma ray of scintillation crystal, also have a certain amount of spuious gamma ray to inject at a certain angle scintillation crystal (as the γ 3 in Fig. 1 and γ 4), by sheathed shield accordingly on light conductor, scintillation crystal or photoelectric commutator, can shield the gamma ray of oblique incidence, retain stratum horizontal direction as far as possible and penetrate next gamma ray, while making to log well, stratigraphic resolution is higher, further improves accuracy and the precision of detector measurement.Therefore, the position of shield can be adjusted according to actual needs.
Further, gamma-ray detector also comprises the first base 31, the second base 32, be arranged on two plugs (the first plug 41 and the second plug 42) at housing two ends and be arranged on two damping parts (the first damping part 51 and the second damping part 52) between plug and photoelectric commutator, wherein, the first base 31 is arranged in housing, be used for carrying the first photoelectric commutator 21, the second base 32 is arranged in housing, be used for carrying the second photoelectric commutator 22, the first damping part 51 is arranged between the first plug 41 and the first base 31, the second damping part 52 is arranged between the second plug 42 and the second base 32.In embodiments of the present invention, damping part can be Compress Spring, can also be other device that can play cushioning effect.
Because scintillation crystal is fragile part, and the optical coupled in gamma-ray detector between each parts also needs certain pretightning force, by damping part is set, realized to the parts in gamma-ray detector are carried out damping and guarantee the optical coupled between each parts, by plug is set, realized all component integrations in housing, become an integral body.
The embodiment of the present invention also provides a kind of disposal route of gamma ray, this disposal route both can be applied to any one gamma-ray detector that embodiment of the present invention foregoing provides, can also be applied to the target gamma-ray detector that any one two ends all have photoelectric commutator, below the disposal route of gamma ray that the embodiment of the present invention is provided be specifically introduced:
Fig. 4 is according to the process flow diagram of the disposal route of the gamma ray of the embodiment of the present invention, and as shown in Figure 4, the disposal route of the gamma ray of this embodiment mainly comprises the steps S502 and S504:
S502: receive the first pulse and the second pulse, wherein, the first pulse is the electric pulse of the first photoelectric commutator output, the second pulse is the electric pulse of the second photoelectric commutator output, the first photoelectric commutator is the photoelectric commutator that is arranged on target gamma-ray detector first end, and the second photoelectric commutator is the photoelectric commutator that is arranged on target gamma-ray detector the second end;
S504: calculate the incoming position of gamma ray and/or the energy of correction gamma ray according to the first pulse and the second pulse.
The disposal route of the gamma ray of the embodiment of the present invention, by to processing from the pulse signal of two photoelectric commutators, realized and from the both sides of target gamma-ray detector, light signal has been received and processed respectively, and then can accurately calculate according to the electric impulse signal corresponding with two light signals the incoming position of gamma ray and/or proofread and correct the energy of gamma ray, solve existing gamma-ray detector axial resolution and the low problem of energy measurement accuracy, and then reached the effect that improves the measuring accuracy of gamma-ray detector.At non-geological exploration field, also can improve by the method for the invention axial resolution and the energy measurement precision of gamma-ray detector.
Because scintillation crystal is different to the energy attenuation of the gamma-ray photon of pass by different light paths and different-energy, so when gamma ray is injected target gamma-ray detector, when the photon inspiring transmits the light path difference of passing by by scintillation crystal in target gamma-ray detector to both ends of the surface, energy attenuation is just different, therefore, by determining amplitude (or area) difference of two pulses, and then calculate the incoming position of gamma ray and/or the energy of correction gamma ray based on this difference, realized and guaranteed the counting accuracy of incoming position and the calibration accuracy of gamma energy.
Particularly, the first pulse and the second pulse are electric pulse, and the embodiment of the present invention mainly provides following three kinds according to the first pulse and the second pulse, to calculate the incoming position of gamma ray and/or the mode of proofreading and correct the energy of gamma ray:
Mode one, specifically comprises the steps:
Step 11: utilize experimental technique to measure the attenuation coefficient of scintillation crystal to the gamma-ray photon of different-energy and different light paths;
Step 12: the digital value of determining voltage amplitude (or area) respective signal of the first electric pulse and the second electric pulse; Concrete, can determine its digital value by analog to digital conversion mode;
Step 13: determine the difference value of two digital signals, this difference value can be difference, ratio, logarithm difference and logarithm ratio; Concrete, the mode that can calculate by processor is determined the difference value of the digital signal that it is corresponding;
Step 14: the position of calculating described gamma ray incident according to the attenuation coefficient of above-mentioned difference value and scintillation crystal;
Step 15: the original signal amplitude (or area) of the attenuation coefficient of passage of scintillation light and two pulses is proofreaied and correct the energy of measured passage of scintillation light according to the incoming position obtaining and scintillation crystal, amplitude after being proofreaied and correct (or area), represents the energy measure of incident gamma ray with this.
Above step finally obtains the incoming position of gamma ray and proofreaies and correct the digital quantity of rear energy, can also be by hardware circuit, utilize following mode two to obtain the analog quantity of above-mentioned information, thereby the analog quantity information of directly exporting incoming position and the rear energy of correction, mode two concrete steps are as follows:
Step 21: utilize experimental technique to measure the attenuation coefficient of scintillation crystal to the gamma-ray photon of different-energy and different light paths;
Step 22: the difference signal of determining the simulating signal that the first electric pulse is corresponding with the voltage amplitude signal (or area of signal) of the second electric pulse, this difference signal can be difference signal, ratio signal, logarithm value signal, concrete, can obtain described difference signal by totalizer or subtracter or multiplier or logarithm device or differential amplifier;
Step 23: according to above-mentioned difference signal and attenuation coefficient and corresponding hardware circuit output represent gamma ray incoming position and proofread and correct after the simulating signal of energy, by miscellaneous equipment, transmit or record this position and energy information.
Above two kinds of methods obtain the attenuation coefficient of scintillation crystal to passage of scintillation light by experiment, then according to two of this attenuation coefficient and acquisition signal amplitudes (or area) difference, obtain the incoming position of gamma ray and the energy information after correction.Meanwhile, can also be not according to attenuation coefficient, the method for calculating by hardware circuit and/or software, three energy measure that obtain gamma ray in the following way, mode three concrete steps are as follows:
Step 31: determine range value or area value that the first pulse and the second pulse are corresponding;
Step 32: the geometrical mean or arithmetic mean value or the weighted mean value that obtain two pulse signals range value (or area value);
Step 33: directly with geometrical mean or arithmetic mean value or the weighted mean value of two pulse signals range value (or area value), replace the range value of the first pulse and/or the second pulse or area value as the energy measure of described gamma ray.
Because crystal is not completely transparent, so having part photon when photon is propagated in crystal is absorbed, gross energy is attenuated, its attenuation coefficient can represent with λ, λ is relevant with the light path that gamma energy and the photon of excitation photon are passed by, the absorption of crystal characteristic of the crystal of different materials or the different size of same material or technique is different, need to test acquisition by reality, and the energy of passage of scintillation light is proportional with the electrical pulse amplitudes (or area) of measuring.
When there being energy, it is pass by crystal two ends respectively while the producing light path of d1, d2 of the passage of scintillation light of E1, the amplitude of two pulses (or area) difference (or ratio) becomes monotonic functional relationship with the energy attenuation difference (or ratio) of two pulses, can obtain thus the optical path difference (or light path ratio) that photon is passed by crystal two ends, according to the length of crystal, can determine the occurrence of d1, d2 again, be equivalent to determine the position of gamma ray incident crystal.Then according to the amplitude of two pulses (or area) and the light path passed by separately and attenuation coefficient, calculate the energy of gamma ray, thereby the measured value of gamma energy is proofreaied and correct.Or can be directly using the arithmetic mean value of two pulse voltage amplitude (or area) or geometrical mean or weighted mean value as the energy measure of current gamma ray, gamma energy is proofreaied and correct.
The above disposal route is the gross energy different phenomenon that decays while passing by different light path in crystal according to passage of scintillation light, utilizes two ends all to have the target gamma-ray detector of photoelectric commutator, obtains two electric signal that have amplitude (or area) difference; Then according to these two electric signal, calculate the position of incident gamma ray and the decay of energy is proofreaied and correct.Therefore, everyly utilize this species diversity and no matter use within which type of mathematical method (such as difference, ratio, logarithm value etc.) all should be included in protection scope of the present invention.
From above description, can find out, because traditional gamma-ray detector can not be told gamma ray incoming position, so in measuring process, axial resolution must be subject to the restriction of scintillation crystal length, and the stratum of resolution can only approach or be greater than the length of scintillation crystal.Relative this kind of traditional gamma-ray detector, gamma-ray detector provided by the present invention, can carry out accurately axial location the position of gamma ray incident and divide, and therefore this detector has improved axial resolution greatly.And the present invention has proofreaied and correct the energy attenuation absorption of passage of scintillation light being caused due to crystal itself, thereby improved the accuracy that gamma energy is measured.In the Detection Techniques field of non-geologic prospecting, also can utilize the present invention to reach the effect that improves gamma-ray detector axial resolution and improve the accuracy of energy measurement.
Further, after according to the energy of the first pulse and the second impulse correction gamma ray, the disposal route of the gamma ray of the embodiment of the present invention also comprises: the gamma ray after correcting energy is applied to destination apparatus, wherein, destination apparatus is for measuring the device of counting rate, energy window or the power spectrum of gamma ray, that is, the energy of gamma ray after overcorrect, can for all measurement gamma ray count rates, can window or the device of power spectrum in.
The foregoing is only the preferred embodiments of the present invention, be not limited to the present invention, for a person skilled in the art, the present invention can have various modifications and variations.Within the spirit and principles in the present invention all, any modification of doing, be equal to replacement, improvement etc., within all should being included in protection scope of the present invention.

Claims (14)

1. a gamma-ray detector, is characterized in that, comprising:
Be numbered A 1to A nn scintillation crystal, wherein, n described scintillation crystal is set up in parallel, and scintillation crystal A iwith scintillation crystal A i+1end-to-end setting, n is more than 2 natural number, i gets 1 successively to n-1;
The first photoelectric commutator, is arranged on scintillation crystal A 1first end, wherein, described scintillation crystal A 1first end be away from scintillation crystal A 2one end;
The second photoelectric commutator, is arranged on scintillation crystal A nfirst end, wherein, described scintillation crystal A nfirst end be away from scintillation crystal A n-1one end; And
Treatment circuit, all be connected with described the second photoelectric commutator with described the first photoelectric commutator, be used for receiving the first pulse and the second pulse, and calculate the incoming position of gamma ray and/or proofread and correct the energy of described gamma ray according to described the first pulse and described the second pulse, wherein, described the first pulse is the pulse of described the first photoelectric commutator output, and described the second pulse is the pulse of described the second photoelectric commutator output.
2. gamma-ray detector according to claim 1, is characterized in that, described gamma-ray detector also comprises:
Light conductor, the number of described light conductor is a plurality of, and wherein, described light conductor is arranged on one of at least position in primary importance, the second place and the 3rd position, described primary importance is the position between every two adjacent described scintillation crystals, and the described second place is described scintillation crystal A 1first end, described the 3rd position is described scintillation crystal A nfirst end.
3. gamma-ray detector according to claim 2, is characterized in that, described gamma-ray detector also comprises:
Housing,
Wherein, n described scintillation crystal, described the first photoelectric commutator, described the second photoelectric commutator and a plurality of described light conductor are all arranged in described housing.
4. gamma-ray detector according to claim 3, is characterized in that, described gamma-ray detector also comprises:
The first base, is arranged in described housing, for carrying described the first photoelectric commutator;
The second base, is arranged in described housing, for carrying described the second photoelectric commutator;
The first plug, is arranged on the first end of described housing;
The second plug, is arranged on the second end of described housing;
The first damping part, is arranged between described the first plug and described the first base; And
The second damping part, is arranged between described the second plug and described the second base.
5. according to the gamma-ray detector described in claim 3 or 4, it is characterized in that, described gamma-ray detector also comprises:
Shield, the number of described shield is a plurality of, wherein, described shield is set in the first circle segment of described housing, the second circle segment, one of at least circle segment place in the 3rd circle segment and the 4th circle segment, wherein, described the first circle segment is the housing parts around light conductor described in each, described the second circle segment is the housing parts around scintillation crystal described in each, described the 3rd circle segment is the housing parts around described the first photoelectric commutator, described the 4th circle segment is the housing parts around described the second photoelectric commutator.
6. gamma-ray detector according to claim 1 and 2, is characterized in that, in n described scintillation crystal, the crystalline material of any two described scintillation crystals is identical or different.
7. gamma-ray detector according to claim 2, is characterized in that, in a plurality of described light conductors, the optical transmittance of any two described light conductors is identical or different.
8. gamma-ray detector according to claim 1, is characterized in that, described the first pulse and described the second pulse are electric pulse, and described treatment circuit comprises:
Amplifier, is all connected with described the second photoelectric commutator with described the first photoelectric commutator, for described the first pulse and described the second pulse are carried out to Hyblid Buffer Amplifier and shaping;
Analog to digital converter, is connected with described amplifier, for gathering pulse height or the area of described the first pulse and described the second pulse, and the output digital signal corresponding with described pulse height or described area; And
Processor, be connected with described analog to digital converter, for calculating the difference value of the described digital signal that represents described the first pulse and described the second pulse, and according to described difference value and described scintillation crystal, the attenuation coefficient of passage of scintillation light is calculated to the incoming position of described gamma ray and the energy after correction.
9. gamma-ray detector according to claim 1, is characterized in that, described the first pulse and described the second pulse are electric pulse, and described treatment circuit comprises:
Amplifier, is all connected with described the second photoelectric commutator with described the first photoelectric commutator, for described the first pulse and described the second pulse are carried out to Hyblid Buffer Amplifier and shaping;
The first logical-arithmetic unit, is connected with described amplifier, for obtaining the difference signal of described the first pulse and described the second pulse;
The second logical-arithmetic unit, is connected with described the first logical-arithmetic unit, for the attenuation coefficient of passage of scintillation light being calculated to the incoming position of described gamma ray and/or the energy of the described gamma ray after correction according to described difference signal and described scintillation crystal.
10. a disposal route for gamma ray, is characterized in that, is applied to target gamma-ray detector, and the two ends of described target gamma-ray detector all have photoelectric commutator, the treating method comprises:
Receive the first pulse and the second pulse, wherein, described the first pulse is the pulse of the first photoelectric commutator output, described the second pulse is the pulse of the second photoelectric commutator output, described the first photoelectric commutator is the photoelectric commutator that is arranged on described target gamma-ray detector first end, and described the second photoelectric commutator is the photoelectric commutator that is arranged on described target gamma-ray detector the second end; And
According to described the first pulse and described the second pulse, calculate the incoming position of described gamma ray and/or proofread and correct the energy of described gamma ray.
11. disposal routes according to claim 10, it is characterized in that, described target gamma-ray detector also comprises scintillation crystal, described the first pulse and described the second pulse are electric pulse, and the energy that calculates the incoming position of described gamma ray and/or proofread and correct described gamma ray according to described the first pulse and described the second pulse comprises:
Determine described the first pulse and corresponding range value or the area value of described the second pulse;
Determine range value or area value and the range value of described the second pulse or the difference value of area value of described the first pulse; And
According to described difference value and described scintillation crystal, the attenuation coefficient of passage of scintillation light is calculated to described incoming position and/or proofread and correct the energy of described gamma ray.
12. disposal routes according to claim 10, it is characterized in that, described target gamma-ray detector also comprises scintillation crystal, described the first pulse and described the second pulse are electric pulse, and the energy that calculates the incoming position of described gamma ray and/or proofread and correct described gamma ray according to described the first pulse and described the second pulse comprises:
Determine described the first pulse and corresponding range signal or the area of signal of described the second pulse;
Determine range signal or area of signal and the range signal of described the second pulse or the difference signal of area of signal of described the first pulse; And
According to described difference signal and described scintillation crystal, the attenuation coefficient of passage of scintillation light is directly exported to the incoming position of described gamma ray and/or the energy of the described gamma ray after correction.
13. disposal routes according to claim 10, is characterized in that, described the first pulse and described the second pulse are electric pulse, according to the energy of gamma ray described in described the first pulse and described the second impulse correction, comprise:
Determine described the first pulse and corresponding range value or the area value of described the second pulse;
Determine range value or area value and the range value of described the second pulse or the geometrical mean of area value or arithmetic mean or the weighted mean value of described the first pulse; And
With range value or area value and the range value of described the second pulse or the geometrical mean of area value or arithmetic mean value or the weighted mean value of described the first pulse, replace the range value of described the first pulse and/or described the second pulse or area value as the energy measure of described gamma ray.
14. disposal routes according to claim 10, is characterized in that, after according to the energy of gamma ray described in described the first pulse and described the second impulse correction, described disposal route also comprises:
Described gamma ray after correcting energy is applied to destination apparatus, and wherein, described destination apparatus is for measuring the device of counting rate, energy window or the power spectrum of described gamma ray.
CN201310567701.9A 2013-11-14 2013-11-14 Gamma ray detector and gamma ray processing method Active CN103558626B (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
CN201310567701.9A CN103558626B (en) 2013-11-14 2013-11-14 Gamma ray detector and gamma ray processing method
PCT/CN2014/077174 WO2015070578A1 (en) 2013-11-14 2014-05-09 Gamma-ray detector and method for processing gamma rays

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201310567701.9A CN103558626B (en) 2013-11-14 2013-11-14 Gamma ray detector and gamma ray processing method

Publications (2)

Publication Number Publication Date
CN103558626A true CN103558626A (en) 2014-02-05
CN103558626B CN103558626B (en) 2017-01-04

Family

ID=50012928

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201310567701.9A Active CN103558626B (en) 2013-11-14 2013-11-14 Gamma ray detector and gamma ray processing method

Country Status (2)

Country Link
CN (1) CN103558626B (en)
WO (1) WO2015070578A1 (en)

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2015070578A1 (en) * 2013-11-14 2015-05-21 北京华脉世纪石油科技有限公司 Gamma-ray detector and method for processing gamma rays
CN106461798A (en) * 2014-05-03 2017-02-22 托尔特克集团有限责任公司 Gamma detector protection for downhole operations
CN107300712A (en) * 2016-04-14 2017-10-27 中国辐射防护研究院 It is a kind of to measure the cascade type scintillator detector of β, gamma spectrum simultaneously
WO2020125371A1 (en) * 2018-12-19 2020-06-25 清华大学 Gamma radiation imaging device and imaging method
CN112415620A (en) * 2020-11-03 2021-02-26 中国海洋石油集团有限公司 Gamma ray detection device and system
CN113126138A (en) * 2021-04-23 2021-07-16 重庆大学 Method for manufacturing high-resolution scintillation screen with multilayer coupling structure and scintillation screen
CN115166844A (en) * 2022-07-06 2022-10-11 核工业航测遥感中心 Combined gamma energy spectrum logging system and gamma energy spectrum logging method

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111119845B (en) * 2019-12-31 2023-10-27 北京环鼎科技有限责任公司 63 gamma-ray spectroscopy three-probe logging instrument and logging method thereof
CN113835114B (en) * 2021-08-25 2024-04-26 吉林大学 Compact high-energy gamma ray anti-coincidence laminated detector

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20100288933A1 (en) * 2008-07-03 2010-11-18 Saint-Gobain Ceramics & Plastics, Inc. Active Voltage Divider for Detector
TW201115176A (en) * 2009-10-30 2011-05-01 Iner Aec Executive Yuan Method for determining penetration effect and detecting efficiency and calibrating detecting efficiency of crystal
WO2013099162A1 (en) * 2011-12-28 2013-07-04 学校法人早稲田大学 Radiation detector
CN203688808U (en) * 2013-11-14 2014-07-02 北京华脉世纪石油科技有限公司 Gamma ray detector

Family Cites Families (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP3227224B2 (en) * 1992-10-09 2001-11-12 日本原子力研究所 Phoswich detector with controllable pulse height and rise time of scintillator output pulse by optical filter
GB0626055D0 (en) * 2006-12-29 2007-11-07 Bae Systems Plc Detection of ionising radiation
CN101737032B (en) * 2010-01-04 2013-01-02 大庆石油管理局 Gamma ray detector in carbon/oxygen spectral logging system with alpha particles
CN101937090B (en) * 2010-08-12 2012-11-07 上海新漫传感技术研究发展有限公司 High-sensitivity wide-range X-gamma ambient dose equivalent rate monitor probe
CN102455431B (en) * 2010-11-25 2013-08-28 上海新漫传感技术研究发展有限公司 Channel type radioactive detector with low detection limit
CN202453508U (en) * 2012-02-02 2012-09-26 中国石油化工股份有限公司 Gamma ray detection device
CN103558626B (en) * 2013-11-14 2017-01-04 北京华脉世纪石油科技有限公司 Gamma ray detector and gamma ray processing method

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20100288933A1 (en) * 2008-07-03 2010-11-18 Saint-Gobain Ceramics & Plastics, Inc. Active Voltage Divider for Detector
TW201115176A (en) * 2009-10-30 2011-05-01 Iner Aec Executive Yuan Method for determining penetration effect and detecting efficiency and calibrating detecting efficiency of crystal
WO2013099162A1 (en) * 2011-12-28 2013-07-04 学校法人早稲田大学 Radiation detector
CN203688808U (en) * 2013-11-14 2014-07-02 北京华脉世纪石油科技有限公司 Gamma ray detector

Cited By (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2015070578A1 (en) * 2013-11-14 2015-05-21 北京华脉世纪石油科技有限公司 Gamma-ray detector and method for processing gamma rays
CN106461798A (en) * 2014-05-03 2017-02-22 托尔特克集团有限责任公司 Gamma detector protection for downhole operations
CN106461798B (en) * 2014-05-03 2020-02-07 托尔特克集团有限责任公司 Gamma detector protection for downhole operations
US10649099B2 (en) 2014-05-03 2020-05-12 Tolteq Group, LLC Gamma detector protection for downhole operations
CN107300712A (en) * 2016-04-14 2017-10-27 中国辐射防护研究院 It is a kind of to measure the cascade type scintillator detector of β, gamma spectrum simultaneously
WO2020125371A1 (en) * 2018-12-19 2020-06-25 清华大学 Gamma radiation imaging device and imaging method
US11644584B2 (en) 2018-12-19 2023-05-09 Tsinghua University Gamma radiation imaging device and imaging method thereof
CN112415620A (en) * 2020-11-03 2021-02-26 中国海洋石油集团有限公司 Gamma ray detection device and system
CN113126138A (en) * 2021-04-23 2021-07-16 重庆大学 Method for manufacturing high-resolution scintillation screen with multilayer coupling structure and scintillation screen
CN113126138B (en) * 2021-04-23 2022-11-11 重庆大学 Method for manufacturing high-resolution scintillation screen with multilayer coupling structure and scintillation screen
CN115166844A (en) * 2022-07-06 2022-10-11 核工业航测遥感中心 Combined gamma energy spectrum logging system and gamma energy spectrum logging method

Also Published As

Publication number Publication date
WO2015070578A1 (en) 2015-05-21
CN103558626B (en) 2017-01-04

Similar Documents

Publication Publication Date Title
CN103558626A (en) Gamma ray detector and gamma ray processing method
CN102640015B (en) Radiation detection system and method of analyzing an electrical pulse output by a radiation detector
US3940610A (en) Natural gamma radiation borehole logging system
US9945965B2 (en) Universal readout for silicon photomultiplier based detectors
US8274056B2 (en) Method, apparatus and system for low-energy beta particle detection
JPS6156471B2 (en)
EP3187901B1 (en) Dose rate measurement device
NO346014B1 (en) Apparatus and method for detecting radiation comprising neutrons and gamma rays
CN1989422B (en) Stabilization of a scintillation detector
CN107247284A (en) The gain correcting device and method of a kind of scintillation detector
KR20190022862A (en) Pixelated gamma detector
GB2050600A (en) Spectrolog microprocessor stripper
CN106443747B (en) Method and apparatus for measuring the arrival time of high-energy photons
CN107076861A (en) Close rate determines device
CN116381772A (en) Real-time energy response correction method, system and terminal for dose rate meter
CN104090293B (en) Based on the fiber array neutron position sensitive detection system and the method that postpone coding
US2830187A (en) Radiation detector
CN203688808U (en) Gamma ray detector
Burnham et al. One dimensional scintillation cameras for positron ECT ring detectors
CN207020320U (en) A kind of gain correcting device of scintillation detector
CN206319881U (en) A kind of new litho-density log system
Maekawa et al. Fiber-optic multipoint radiation sensing system using waveguide scintillators
Anzorena et al. Simulation and experimental validation of optimum read-out electronics design for scintillator bar cosmic ray telescope
CN108196293A (en) One kind is based on scintillator detector dosage rate detection method
RU2751458C1 (en) Method for measuring intensity of radiation of unknown composition

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
C14 Grant of patent or utility model
GR01 Patent grant