CN211603562U - Radiation detection device, gamma neutron measuring instrument and image positioning system - Google Patents
Radiation detection device, gamma neutron measuring instrument and image positioning system Download PDFInfo
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- CN211603562U CN211603562U CN202020239762.8U CN202020239762U CN211603562U CN 211603562 U CN211603562 U CN 211603562U CN 202020239762 U CN202020239762 U CN 202020239762U CN 211603562 U CN211603562 U CN 211603562U
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Abstract
The utility model relates to the technical field of radiation detection, in particular to a radiation detection device, a gamma neutron measuring instrument and an image positioning system, wherein the radiation detection device comprises lithium glass, a scintillation crystal positioned at the upstream of the lithium glass and a moderating body positioned at the upstream; the radiation detection device has a first radiation path, a second radiation path and a third radiation path; in the case of a first radiation path, the gamma rays pass through the scintillation crystal and the lithium glass in sequence, producing a first type of fluorescence photons; in the case of a second radiation path, gamma rays are radiated to the lithium glass, producing a second type of fluorescence photons; in the case of the third radiation path, the neutron rays pass through the moderator and the lithium glass in sequence, producing a third type of fluorescence photon. The utility model provides a technical scheme can realize gamma radiation simultaneously and survey and neutron, has greatly saved the space, helps the miniaturization of equipment, has reduced the research and development cost simultaneously.
Description
Technical Field
The utility model belongs to the technical field of the radiation detection technique and specifically relates to a radiation detection device, gamma neutron measuring apparatu and image positioning system are related to.
Background
The portable gamma and neutron detector is widely applied to occasions such as airports, stations, docks and the like, can be flexibly deployed, and can be used for radioactivity level detection and radioactive source positioning of goods and personnel.
Early gamma radiation detectors, which are based on GM detectors, have low detection sensitivity and are only capable of indicating radiation dose rates without being able to identify nuclides, are currently replaced by sodium iodide detectors and lanthanum bromide detectors, and the latter two detectors have high sensitivity and can identify nuclides by gamma spectroscopy. The gamma camera equipment which is started in recent years uses an array crystal detector, applies the technology of real-time fusion of radiation images and optical images, can position a radioactive source, and is a new development direction of miniaturized gamma and neutron detectors.
Early neutron detector is given priority to He-3 neutron detector, and detector and moderator volume are all great, often lead to the equipment to be heavy if use in portable equipment, do not easily carry. The lithium glass detector has the advantages of high sensitivity, small volume and low cost, and is widely applied to portable neutron detectors.
The prior art gamma detector and neutron detector act as separate detection systems: generally, a gamma radiation detector mainly comprises a scintillation crystal, an optical collection system, a photoelectric device, a high-voltage circuit, a signal processing circuit and the like; the neutron detector mainly comprises a moderator, lithium glass, an optical collection system, a photoelectric device, a high-voltage circuit, a signal processing circuit and the like; the two systems operate independently and do not coincide with each other.
SUMMERY OF THE UTILITY MODEL
An object of the utility model is to provide a radiation detection device, gamma neutron measuring apparatu and image positioning system to current gamma radiation detection and neutron detection that exist among the alleviating prior art are two sets of independent systems, do not coincide each other, therefore have the inconvenient, bulky scheduling problem of use.
In order to solve the technical problem, the utility model provides a technical scheme lies in:
a radiation detection device comprising a lithium glass, a scintillation crystal located upstream of the lithium glass, and a moderator located upstream; the radiation detection device has a first radiation path, a second radiation path, and a third radiation path;
in the case of the first radiation path, gamma rays pass through the scintillation crystal and the lithium glass in sequence, producing first type fluorescence photons;
in the case of the second radiation path, gamma rays are radiated to the lithium glass, generating fluorescence photons of a second type;
in the case of the third radiation path, neutron rays pass through the moderator and the lithium glass in sequence, producing a third type of fluorescence photon.
Further, in the present invention,
the photoelectric device is arranged at the downstream of the lithium glass and is used for multiplying the fluorescence photon signal and outputting a pulse signal.
Further, in the present invention,
the optoelectronic device comprises a photomultiplier tube,
the first type of fluorescence photons output a first type of pulse signal after passing through the photomultiplier;
the second type of fluorescence photons output a second type of pulse signals after passing through the photomultiplier;
and the third type of fluorescence photons output a third type of pulse signals after passing through the photomultiplier.
Further, in the present invention,
the signal processing circuit is used for carrying out discrimination processing on the first type pulse signals, the second type pulse signals and the third type pulse signals.
Further, in the present invention,
the material of the moderator comprises polyethylene which is a low atomic number material.
Further, in the present invention,
the scintillation crystal comprises NaI crystal or CsI crystal, LaBr3Crystal and YSO.
A gamma-neutron measuring instrument comprises a moderator, a scintillation crystal, lithium glass and a photomultiplier;
the lithium glass is arranged between the scintillation crystal and the photomultiplier;
the moderator surrounds a portion of the scintillation crystal, the lithium glass, and a portion of the photomultiplier tube.
An image positioning system is provided, which is capable of positioning a plurality of images,
comprises a moderator, a scintillation crystal, lithium glass and a photomultiplier;
the lithium glass is arranged between the scintillation crystal and the photomultiplier;
the moderator is annularly disposed on both sides of the scintillation crystal.
Further, in the present invention,
still include lead shielding, lead shielding annular deploys scintillation crystal both sides, just the moderator pastes in lead shielding's the outside.
Further, in the present invention,
the scintillation crystal is an array crystal.
Technical scheme more than combining, the utility model discloses the beneficial effect analysis that can reach as follows:
the utility model provides a radiation detection device, which comprises lithium glass, a scintillation crystal positioned at the upstream of the lithium glass and a moderator positioned at the upstream; the radiation detection device has a first radiation path, a second radiation path, and a third radiation path;
in the case of the first radiation path, gamma rays pass through the scintillation crystal and the lithium glass in sequence, producing first type fluorescence photons;
in the case of the second radiation path, gamma rays are radiated to the lithium glass, generating fluorescence photons of a second type;
in the case of the third radiation path, neutron rays pass through the moderator and the lithium glass in sequence, producing a third type of fluorescence photon.
The utility model provides an among the technical scheme, lithium glass had both replaced the light guide plate among the former gamma radiation detector, can realize neutron detection again simultaneously, had greatly saved the space, helped the miniaturization of equipment, had reduced the research and development cost simultaneously.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings used in the embodiments or the technical solutions in the prior art will be briefly described below, and it is obvious that the drawings in the following description are some embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to these drawings without creative efforts.
Fig. 1 is a schematic diagram of a radiation detection apparatus according to an embodiment of the present invention;
fig. 2 is a schematic structural diagram of a gamma neutron measurement instrument provided in an embodiment of the present invention;
fig. 3 is a schematic structural diagram of an image positioning system according to an embodiment of the present invention.
Icon: 100-scintillation crystals; 200-moderator; 300-lithium glass; 400-a photomultiplier tube; 500-a signal processing circuit; 600-lead shielding; 700-a high voltage circuit; 800-code board.
Detailed Description
The technical solution of the present invention will be described clearly and completely with reference to the accompanying drawings, and obviously, the described embodiments are some, but not all embodiments of the present invention. Based on the embodiments in the present invention, all other embodiments obtained by a person skilled in the art without creative work belong to the protection scope of the present invention.
In the description of the present invention, it should be noted that the terms "center", "upper", "lower", "left", "right", "vertical", "horizontal", "inner", "outer", and the like indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings, and are only for convenience of description and simplification of description, but do not indicate or imply that the device or element referred to must have a specific orientation, be constructed and operated in a specific orientation, and thus, should not be construed as limiting the present invention. Furthermore, the terms "first," "second," and "third" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.
In the description of the present invention, it is to be noted that, unless otherwise explicitly specified or limited, the terms "mounted," "connected," and "connected" are to be construed broadly, and may be, for example, fixedly connected, detachably connected, or integrally connected; can be mechanically or electrically connected; they may be connected directly or indirectly through intervening media, or they may be interconnected between two elements. The specific meaning of the above terms in the present invention can be understood in specific cases to those skilled in the art.
Example one
The present embodiment provides a radiation detection device, please refer to fig. 1, which includes a lithium glass 300, a scintillation crystal 100 located upstream of the lithium glass 300, and a moderator 200 located upstream; the radiation detection device has a first radiation path, a second radiation path and a third radiation path;
in the case of the first radiation path, the gamma rays pass through the scintillation crystal 100 and the lithium glass 300 in sequence, producing a first type of fluorescence photons;
in the case of the second radiation path, gamma rays are radiated to the lithium glass 300, generating fluorescence photons of the second type;
in the case of the third radiation path, the neutron rays pass through the moderator 200 and the lithium glass 300 in sequence, producing a third type of fluorescence photon.
The utility model provides an among the technical scheme, lithium glass 300 had both replaced the light guide plate among the former gamma radiation detector, can realize neutron detection again simultaneously, had greatly saved the space, helped the miniaturization of equipment, had reduced the research and development cost simultaneously.
In an alternative to this embodiment, it is preferable that,
the lithium glass 300 scintillator is in a sheet shape, the optional thickness is 2-10 mm, and the light transmission is good. The gamma rays and the n rays both can excite fluorescence photons when being irradiated on the lithium glass 300, the fluorescence photons generated by the gamma rays are called second type fluorescence photons, and the fluorescence photons generated by the n rays are called third type fluorescence photons.
In an alternative to this embodiment, it is preferable that,
the radiation detection device further comprises a photoelectric device, wherein the photoelectric device is arranged at the downstream of the lithium glass 300 and is used for multiplying the fluorescence photon signal and then outputting a pulse signal. The photoelectric device can select a model with a proper size according to the sizes of the scintillation crystal 100 and the lithium glass 300.
Further, in the present invention,
the optoelectronic device includes a photomultiplier tube 400 that,
the first type of fluorescence photons output a first type of pulse signal after passing through the photomultiplier 400;
the second type of fluorescence photons output a second type of pulse signals after passing through the photomultiplier 400;
the third type of fluorescence photons output a third type of pulse signals after passing through the photomultiplier tube 400.
The photomultiplier 400 may be a conventional photomultiplier 400(PMT), a position sensitive photomultiplier 400(PSPMT), or a silicon photomultiplier 400(sipm), and fluorescent photons enter the photomultiplier photocathode to generate photoelectrons, which are multiplied by the photomultiplier to output pulse signals and then are connected to the signal processing circuit 500.
In an alternative to this embodiment, it is preferable that,
the radiation detection apparatus further includes a signal processing circuit 500, and the signal processing circuit 500 is used for performing discrimination processing on the first type pulse signal, the second type pulse signal and the third type pulse signal.
The signal processing circuit 500 preferably includes a high voltage circuit 700, and the high voltage circuit 700 provides an operating voltage for the multiplier so that the multiplier can operate normally.
The signal processing circuit 500 preferably includes signal amplification, shaping, and discrimination functions, and three pulse signals generated by the scintillation crystal 100 and the lithium glass 300 need to be discriminated to obtain effective gamma and n-ray monitoring results. And discriminating the three pulse signals through pulse waveform differences, and calculating the environmental radiation change.
In an alternative to this embodiment, it is preferable that,
the material of the moderator 200 includes a low atomic number material, polyethylene. Wrapping around lithium glass 300, neutrons strike moderator 200 with probability to be moderated into thermal neutrons increasing the reaction cross section.
In an alternative to this embodiment, it is preferable that,
the scintillator crystal 100 includes one of NaI (sodium iodide) crystal or CsI (cesium iodide) crystal, LaBr3 (lanthanum bromide), YSO (yttrium silicate), and the like. The scintillation crystal 100 can be either a monolithic crystal or a tiled crystal array. The gamma rays irradiate the scintillation crystal 100 to excite fluorescence photons, called first type fluorescence photons, and the first type fluorescence photons enter the photomultiplier 400 through the lithium glass 300.
Example 2
The present embodiment provides a gamma-neutron measurement instrument, specifically referring to fig. 2, the gamma-neutron measurement instrument adopts the detection principle of embodiment 1 (fig. 1), and specifically includes a moderator 200, a scintillation crystal 100, a lithium glass 300, and a photomultiplier 400;
the lithium glass 300 is disposed between the scintillation crystal 100 and the photomultiplier 400;
the moderator 200 surrounds portions of the scintillation crystal 100, the lithium glass 300, and portions of the photomultiplier tube 400.
In an alternative to this embodiment, it is preferable that,
the moderator 200 is made of polyethylene with a low atomic number material, and is wrapped around part of the sodium iodide scintillation crystal 100, the lithium glass 300 and part of the photomultiplier 400, and neutrons are irradiated on the moderator 200 and are moderated into thermal neutrons with probability to increase the reaction section.
In an alternative to this embodiment, it is preferable that,
the scintillation crystal 100 is a 2-inch NaI crystal, and can be replaced by other NaI crystals or CsI crystals or LaBr3 crystals, gamma rays irradiate the scintillation crystal 100 to excite fluorescence photons, called first-class fluorescence photons, and the first-class fluorescence photons enter the photomultiplier 400 through the lithium glass 300.
In an alternative to this embodiment, it is preferable that,
the lithium glass 300 scintillator is in the form of a thin sheet, and the lithium glass 300 is selected to have a thickness of 5mm, good light transmission, a diameter of 2 inches or other dimensions consistent with the crystal. The gamma rays and the n rays both can excite fluorescence photons when being irradiated on the lithium glass 300, the fluorescence photons generated by the gamma rays are called second type fluorescence photons, and the fluorescence photons generated by the n rays are called third type fluorescence photons. The first, second, and third types of fluorescence photons all enter photomultiplier tube 400 through lithium glass 300.
In an alternative to this embodiment, it is preferable that,
the photomultiplier tube 400 may be of a size selected according to the size of the scintillation crystal 100 and the lithium glass 300. The fluorescence photons enter the multiplier photocathode to generate photoelectrons, and the photoelectrons are multiplied by the multiplier tube in the multiplier tube beating stage to output pulse signals and are connected to the signal processing circuit 500. The first type of fluorescence photons form a first type of pulse signal after being multiplied by the multiplier tube, the second type of fluorescence photons form a second type of pulse signal after being multiplied by the multiplier tube, and the third type of fluorescence photons form a third type of pulse signal after being multiplied by the multiplier tube.
Example 3
The present embodiment provides an image positioning system, specifically referring to fig. 3, the image positioning system adopts the detection principle of embodiment 1, and specifically includes a moderator 200, a scintillation crystal 100, a lithium glass 300, and a photomultiplier 400;
the lithium glass 300 is disposed between the scintillation crystal 100 and the photomultiplier 400;
the moderators 200 are disposed annularly on both sides of the scintillator crystal 100.
Further, in the present invention,
the image positioning system further comprises a lead shield 600, wherein the lead shield 600 is annularly arranged on two sides of the scintillation crystal 100, and the slowing body 200 is attached to the outer side of the lead shield 600. Lead shielding 600 is used to prevent environmental gamma rays from affecting the imaging of the radioactive source.
Further, in the present invention,
the scintillation crystal 100 is an array crystal, preferably a 21 × 21YSO array crystal, or may be a 17 × 17, 13 × 13 YSO array crystal or other array crystal of other specifications. The array crystal may be formed from a plurality of crystal arrays, or a crystal array cut from a single crystal.
Further, in the present invention,
the image localization system also includes an encoder plate 800, the encoder plate 800 being positioned on top of the annular region formed by the moderator 200.
In an alternative to this embodiment, it is preferable that,
the moderator 200 material includes a low atomic number material, such as polyethylene, disposed proximate to the lead shield 600, which moderates the thermal neutrons to increase the reaction cross-section with probability that neutrons strike the moderator 200.
In an alternative to this embodiment, it is preferable that,
the lithium glass 300 scintillator is in a sheet shape, the thickness of the lithium glass 300 is selected to be 5mm, the light transmittance is good, and the shape of the lithium glass 300 is consistent with that of the scintillation crystal 100. The gamma rays and the n rays both can excite fluorescence photons when being irradiated on the lithium glass 300, the fluorescence photons generated by the gamma rays are called second type fluorescence photons, and the fluorescence photons generated by the n rays are called third type fluorescence photons. The first, second, and third types of fluorescence photons all enter photomultiplier tube 400 through lithium glass 300.
In an alternative to this embodiment, it is preferable that,
the silicon photomultiplier is arranged in an 8-by-8 array, and the overall size of the arranged silicon photomultiplier is consistent with that of the lithium glass 300. The fluorescence photons enter the multiplier photocathode to generate photoelectrons, and the photoelectrons are multiplied by the multiplier tube in the multiplier tube beating stage to output pulse signals and are connected to the signal processing circuit 500. The first type of fluorescence photons form a first type of pulse signal after being multiplied by the multiplier tube, the second type of fluorescence photons form a second type of pulse signal after being multiplied by the multiplier tube, and the third type of fluorescence photons form a third type of pulse signal after being multiplied by the multiplier tube.
Finally, it should be noted that: the above embodiments are only used to illustrate the technical solution of the present invention, and not to limit the same; although the present invention has been described in detail with reference to the foregoing embodiments, it should be understood by those skilled in the art that: the technical solutions described in the foregoing embodiments may still be modified, or some or all of the technical features may be equivalently replaced; such modifications and substitutions do not depart from the spirit and scope of the present invention.
Claims (10)
1. A radiation detection device comprising a lithium glass, a scintillation crystal located upstream of the lithium glass, and a moderator located upstream; the radiation detection device has a first radiation path, a second radiation path, and a third radiation path;
in the case of the first radiation path, gamma rays pass through the scintillation crystal and the lithium glass in sequence, producing first type fluorescence photons;
in the case of the second radiation path, gamma rays are radiated to the lithium glass, generating fluorescence photons of a second type;
in the case of the third radiation path, neutron rays pass through the moderator and the lithium glass in sequence, producing a third type of fluorescence photon.
2. The radiation detection apparatus of claim 1, wherein:
the photoelectric device is arranged at the downstream of the lithium glass and is used for multiplying the fluorescence photon signal and outputting a pulse signal.
3. The radiation detection apparatus of claim 2, wherein:
the optoelectronic device comprises a photomultiplier tube,
the first type of fluorescence photons output a first type of pulse signal after passing through the photomultiplier;
the second type of fluorescence photons output a second type of pulse signals after passing through the photomultiplier;
and the third type of fluorescence photons output a third type of pulse signals after passing through the photomultiplier.
4. The radiation detection apparatus of claim 3,
the signal processing circuit is used for carrying out discrimination processing on the first type pulse signals, the second type pulse signals and the third type pulse signals.
5. The radiation detection apparatus of claim 1,
the material of the moderator comprises polyethylene which is a low atomic number material.
6. The radiation detection apparatus of claim 1,
the scintillation crystal comprises NaI crystal, CsI crystal, LaBr3 crystal or YSO.
7. The gamma-neutron measuring instrument is characterized by comprising a moderator, a scintillation crystal, lithium glass and a photomultiplier;
the lithium glass is arranged between the scintillation crystal and the photomultiplier;
the moderator surrounds a portion of the scintillation crystal, the lithium glass, and a portion of the photomultiplier tube.
8. An image localization system, characterized in that,
comprises a moderator, a scintillation crystal, lithium glass and a photomultiplier;
the lithium glass is arranged between the scintillation crystal and the photomultiplier;
the moderator is annularly disposed on both sides of the scintillation crystal.
9. The image localization system of claim 8,
still include lead shielding, lead shielding annular deploys scintillation crystal both sides, just the moderator pastes in lead shielding's the outside.
10. Image localization system according to claim 8 or 9,
the scintillation crystal is an array crystal.
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| CN202020239762.8U CN211603562U (en) | 2020-03-02 | 2020-03-02 | Radiation detection device, gamma neutron measuring instrument and image positioning system |
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