CN212483883U - Fast reactor covering gas gamma activity monitor - Google Patents
Fast reactor covering gas gamma activity monitor Download PDFInfo
- Publication number
- CN212483883U CN212483883U CN202021350288.2U CN202021350288U CN212483883U CN 212483883 U CN212483883 U CN 212483883U CN 202021350288 U CN202021350288 U CN 202021350288U CN 212483883 U CN212483883 U CN 212483883U
- Authority
- CN
- China
- Prior art keywords
- resistor
- operational amplifier
- path
- capacitor
- power supply
- 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.)
- Active
Links
Images
Landscapes
- Measurement Of Radiation (AREA)
Abstract
The utility model discloses a fast reactor covering gas gamma activity monitor, which comprises a shielding shell sleeved on a gas sampling pipeline and a radiation detection assembly arranged in the shielding shell and matched with the gas sampling pipeline; the shielding shell comprises a front cover, a shielding cylinder and a rear cover which are sequentially connected, a first through groove matched with the gas sampling pipeline is formed in one end, matched with the shielding cylinder, of the front cover, a second through groove matched with the gas sampling pipeline is formed in the shielding cylinder, and an active detection device is arranged on the side wall of the shielding cylinder. The utility model has the advantages that the shielding shell is sleeved on the gas sampling pipeline, and the radiation detection assembly is arranged in the shielding shell to work, so that the monitoring of the gamma activity of the covering gas is not influenced by the radiation environment at the high background of the monitoring process room, and the accuracy of the detection is ensured; whether set up embedded source and source simultaneously and examine the device and discern radiation detection subassembly and have damaged to in time change the maintenance, guarantee the degree of accuracy of surveying, the practicality is strong, convenient to popularize and use.
Description
Technical Field
The utility model belongs to the technical field of fast reactor covers gaseous gamma activity ratio monitoring, concretely relates to fast reactor covers gaseous gamma activity ratio monitor.
Background
Under the operating condition of the fast neutron reactor, the fuel damage gas covering system continuously pumps covering gas in the reactor container to a covering gas radioactivity monitoring process room outside the reactor container through a pipeline. The traditional fast reactor covering gas monitoring method is characterized in that a general laboratory gamma spectrometer is used for measuring covering gas of a process room pipeline, fission nuclides are directly analyzed, original data are measured by the laboratory instrument, the original data need to be exported for data analysis, and meanwhile the laboratory instrument gamma spectrometer is in a high background radiation environment in the process room, so that a detector and a subsequent electronic circuit are easily influenced, and the measurement result is inaccurate.
SUMMERY OF THE UTILITY MODEL
The utility model aims to solve the technical problem that the defects in the prior art are overcome, and the fast reactor covering gas gamma activity monitor is provided, which has the advantages of simple structure, reasonable design and strong practicability, wherein the shielding shell is sleeved on the gas sampling pipeline, and the radiation detection assembly is arranged in the shielding shell to work, so that the covering gas gamma activity monitoring is not influenced by the high background radiation environment in the monitoring process room, and the detection accuracy is ensured; whether set up embedded source and source simultaneously and examine the device and discern radiation detection subassembly and have damaged to in time change the maintenance, guarantee the degree of accuracy of surveying, the practicality is strong, convenient to popularize and use.
In order to solve the technical problem, the utility model discloses a technical scheme is: a fast reactor covering gas gamma activity monitor is characterized in that: the radiation detection device comprises a shielding shell sleeved on a gas sampling pipeline and a radiation detection assembly arranged in the shielding shell and matched with the gas sampling pipeline;
the shielding shell comprises a front cover, a shielding cylinder and a rear cover which are sequentially connected, the radiation detection assembly is arranged in the shielding cylinder, a first through groove matched with the gas sampling pipeline is formed in one end, matched with the shielding cylinder, of the front cover, a second through groove matched with the gas sampling pipeline is formed in the shielding cylinder, a source detection through hole matched with the detection end of the radiation detection assembly and communicated with the inside of the shielding cylinder is formed in the side wall of the shielding cylinder, an active detection device is filled in the source detection through hole, and the source detection device comprises a T-shaped lead plug and a radioactive source arranged at one end, close to the inside of the shielding cylinder, of the T-shaped lead plug;
the radiation detection assembly comprises a crystal, a photomultiplier and a signal processing circuit board which are sequentially connected, an embedded source is arranged at one end of the crystal matched with the gas sampling pipeline, a pre-amplification circuit and a main amplification circuit are integrated on the signal processing circuit board, and the output end of the photomultiplier is connected with the input end of the pre-amplification circuit.
The fast reactor covering gas gamma activity monitor is characterized in that: the preamplifier circuit comprises a capacitor C18, a PNP triode Q1 and a PNP triode Q2, wherein one end of a capacitor C18 is connected with the anode of a photomultiplier, the other end of the capacitor C18 is connected with the base of the PNP triode Q1, the photomultiplier adopts positive high voltage power supply, the emitter of the PNP triode Q1 is divided into three paths, one path is sequentially connected with a +12V power supply through a resistor R5 and a resistor R1, the second path is connected with the base of the PNP triode Q2 through a resistor R9, the third path is sequentially connected with the connecting ends of a resistor R5 and a resistor R1 through a capacitor C9 and a resistor R4, the connecting end of a capacitor C9 and a resistor R4 is divided into two paths, one path is grounded through a resistor R17, the other path is connected with the base of a PNP triode Q1 through a resistor R13, the collector of the PNP triode Q1 is divided into two paths, one path is grounded through a resistor R18, the emitter of the PNP triode Q18 is connected with the emitter of the PNP triode Q36, one path is connected with the connecting end of the resistor R5 and the resistor R1 through the resistor R3, the other path is connected with one end of the resistor R10 through the capacitor C10, and the other end of the resistor R10 is the output end of the pre-amplification circuit.
The fast reactor covering gas gamma activity monitor is characterized in that: the main amplifying circuit comprises an operational amplifier U1, an operational amplifier U2 and an operational amplifier U3, wherein the non-inverting input end of the operational amplifier U1 is divided into two paths, one path is connected with the output end of the pre-amplifying circuit through a capacitor C11, the other path is grounded through a resistor R14, the output end of the operational amplifier U1 is divided into two paths, one path is connected with the inverting input end of the operational amplifier U1 through a resistor R2, the other path is sequentially connected with the inverting input end of the operational amplifier U2 through a capacitor C12 and a resistor R11, the positive power supply electrode of the operational amplifier U1 is connected with a +5V power supply, and the negative power supply electrode of the operational amplifier U1 is connected with a-5V power supply; the non-inverting input end of the operational amplifier U2 is grounded through a resistor R16, the output end of the operational amplifier U2 is divided into two paths, one path is connected with the inverting input end of the operational amplifier U2 through a resistor R6, the other path is connected with the non-inverting input end of the operational amplifier U3 through a resistor R12, the positive electrode of a power supply of the operational amplifier U2 is connected with a +5V power supply, and the negative electrode of the power supply of the operational amplifier U2 is grounded; the non-inverting input end of the operational amplifier U3 is grounded through a capacitor C16, the inverting input end of the operational amplifier U3 is grounded through a resistor R7, the output end of the operational amplifier U3 is divided into two paths, one path is connected with the inverting input end of the operational amplifier U3 through a resistor R8, the other path is grounded through a capacitor C13 and a resistor R15 in sequence, the connecting end of a capacitor C13 and a resistor R15 serves as the output end of the main amplifying circuit, the positive power supply electrode of the operational amplifier U3 is connected with a +5V power supply, and the negative power supply electrode of the operational amplifier U3 is grounded.
The fast reactor covering gas gamma activity monitor is characterized in that: the shielding cylinder and the front cover and the shielding cylinder and the rear cover are connected through hinges.
The fast reactor covering gas gamma activity monitor is characterized in that: the bottom of the shielding shell is provided with a mounting seat.
The fast reactor covering gas gamma activity monitor is characterized in that: and one end of the rear cover, which is far away from the hinge, is provided with a groove.
The fast reactor covering gas gamma activity monitor is characterized in that: the crystal is a NaI scintillation crystal with the diameter of 50mm multiplied by 50mm, and the photomultiplier is a CR105-03 type photomultiplier.
The fast reactor covering gas gamma activity monitor is characterized in that: the embedded source is an americium source.
The fast reactor covering gas gamma activity monitor is characterized in that: the rear cover is provided with a plug, one end of the plug penetrates through the rear cover to be connected with the signal processing circuit board, and the other end of the plug is connected with the computer through a cable.
Compared with the prior art, the utility model has the following advantage:
1. the utility model discloses a establish the shield shell cover on gaseous sample pipeline, the radiation detection subassembly sets up work in the shield shell, makes the monitoring of cover gas gamma activity degree not receive the influence of the high background radiation environment between the monitoring technology, guarantees the accuracy of surveying.
2. The utility model discloses a front side sets up embedded source on the crystal, and the radiation signal that the embedded source of crystal discernment sent converts the light signal into to follow-up photomultiplier signal conversion, and the embedded source detection data after signal processing of photomultiplier's output is as the reference data, and it has the damage to discern the radiation detection subassembly, so that the maintenance of in time changing of equipment, the assurance accuracy of surveying, excellent in use effect.
3. The utility model discloses a set up the source and examine the device, insert the source that is fixed with the radiation source and examine the device when needs source is examined, judge whether there is the damage radiation detection subassembly according to the radioactivity of the radiation source that the radiation detection subassembly detected to the in time change maintenance of equipment guarantees the detection degree of accuracy, excellent in use effect.
To sum up, the utility model has simple structure, reasonable design and strong practicability, and the radiation detection component is arranged in the shielding shell to work by sleeving the shielding shell on the gas sampling pipeline, so that the monitoring of the gamma activity of the covering gas is not influenced by the high background radiation environment between the monitoring processes, and the detection accuracy is ensured; whether set up embedded source and source simultaneously and examine the device and discern radiation detection subassembly and have damaged to in time change the maintenance, guarantee the degree of accuracy of surveying, the practicality is strong, convenient to popularize and use.
The technical solution of the present invention is further described in detail by the accompanying drawings and examples.
Drawings
Fig. 1 is a schematic structural diagram of the present invention.
Fig. 2 is a view taken along direction a in fig. 1.
Fig. 3 is a sectional view B-B in fig. 2.
Fig. 4 is a usage state diagram of the present invention.
Fig. 5 is a schematic circuit diagram of the preamplifier circuit of the present invention.
Fig. 6 is a schematic circuit diagram of the main amplifier circuit of the present invention.
Description of reference numerals:
1-a gas sampling pipe; 2-front cover; 3-a shielding cylinder;
4-rear cover; 5-a first through groove; 6-a second through groove;
7-T type lead plug; 8-a radioactive source; 9-crystal;
10-a photomultiplier tube; 11-a signal processing circuit board; 12-an embedded source;
13-a hinge; 14-a mounting seat; 15-a groove;
16-plug.
Detailed Description
As shown in fig. 1 to 4, the present invention includes a shielding shell sleeved on a gas sampling pipe 1 and a radiation detection assembly disposed in the shielding shell and matched with the gas sampling pipe 1;
the shielding shell comprises a front cover 2, a shielding cylinder 3 and a rear cover 4 which are sequentially connected, the radiation detection assembly is arranged in the shielding cylinder 3, one end, matched with the shielding cylinder 3, of the front cover 2 is provided with a first through groove 5 matched with the gas sampling pipeline 1, the shielding cylinder 3 is provided with a second through groove 6 matched with the gas sampling pipeline 1, the side wall of the shielding cylinder 3 is provided with a source detection through hole matched with the detection end of the radiation detection assembly and communicated with the inside of the shielding cylinder 3, the source detection through hole is filled with a source detection device, and the source detection device comprises a T-shaped lead plug 7 and a radioactive source 8 arranged at one end, close to the inside of the shielding cylinder 3, of the T-shaped lead plug 7;
the radiation detection assembly comprises a crystal 9, a photomultiplier 10 and a signal processing circuit board 11 which are sequentially connected, an embedded source 12 is arranged at one end, matched with the gas sampling pipeline 1, of the crystal 9, a pre-amplification circuit and a main amplification circuit are integrated on the signal processing circuit board 11, and the output end of the photomultiplier 10 is connected with the input end of the pre-amplification circuit.
In the embodiment, the shielding shell is formed by pouring low-background old lead with the thickness of 7 cm;
it should be noted that, in the normal working state of the device, the inside of the source detection through hole is filled with a lead rod with the same aperture as that of the source detection through hole, when whether the radiation detection assembly needs to be detected to be in the normal working state or not, the lead rod is pulled out and inserted into the source detection device, and one end of the T-shaped lead plug 7, which is far away from the radioactive source 8, is clamped outside the shielding cylinder 3, so that the T-shaped lead plug 7 is prevented from excessively penetrating into the shielding cylinder 3 to cause damage to the radioactive source 8;
it should be noted that the installation of the gas sampling pipeline 1 is facilitated by arranging the first through groove 5 and the second through groove 6, the first through groove 5 and the second through groove 6 are spliced to form a circular through hole with the same pipe diameter as that of the gas sampling pipeline 1, the shielding performance of the shielding cylinder 3 is ensured, and meanwhile, the inaccurate monitoring result caused by the fact that the gas sampling pipeline 1 moves up and down in the device in the monitoring process is prevented, the operation is convenient, and the using effect is good;
the radioactive source 8 is defined as137A Cs radioactive source;
it should be noted that, by sleeving the shielding shell on the gas sampling pipeline 1 and arranging the radiation detection assembly in the shielding shell to work, the monitoring of the gamma activity of the covering gas is not affected by the high-background radiation environment of the monitoring process room, and the detection accuracy is ensured;
the embedded source 12 is arranged on the front side of the crystal 9, the crystal 9 identifies a radiation signal emitted by the embedded source 12 and converts the radiation signal into an optical signal, so that the signal of a subsequent photomultiplier tube is converted, the detection data of the embedded source 12, which is obtained by processing the signal at the output end of the photomultiplier tube, is used as reference data, whether a radiation detection assembly is damaged or not is identified, so that the equipment can be replaced and maintained in time, the detection accuracy is ensured, and the using effect is good;
by arranging the source detection device, the source detection device fixed with the radioactive source 8 is inserted when source detection is needed, and whether the radiation detection assembly is damaged or not is judged according to the radioactivity of the radioactive source 8 detected by the radiation detection assembly, so that the equipment can be replaced and maintained in time, the detection accuracy is ensured, and the using effect is good;
in this embodiment, as shown in fig. 5, the preamplifier circuit includes a capacitor C18, a PNP transistor Q1, and a PNP transistor Q2, one end of the capacitor C18 is connected to the anode of the photomultiplier tube 10, the other end of the capacitor C18 is connected to the base of the PNP transistor Q1, the photomultiplier tube 10 is powered by a positive high voltage, the emitter of the PNP transistor Q1 is divided into three parts, one part is connected to the +12V power supply through a resistor R5 and a resistor R1 in turn, the second part is connected to the base of the PNP transistor Q2 through a resistor R9, the third part is connected to the connection end of a resistor R5 and a resistor R1 through a capacitor C9 and a resistor R4 in turn, the connection end of the capacitor C9 and the resistor 686r 9 is divided into two parts, one part is grounded through a resistor R17, the other part is connected to the base of the PNP transistor Q1 through a resistor R13, the collector of the PNP transistor Q1 is divided into two parts, one part is grounded through a resistor R18, the other part is grounded through a resistor R36, the emitting electrode of the PNP triode Q2 is divided into two paths, one path is connected with the connecting end of the resistor R5 and the resistor R1 through the resistor R3, the other path is connected with one end of the resistor R10 through the capacitor C10, and the other end of the resistor R10 is the output end of the pre-amplification circuit.
As shown in fig. 5, in actual wiring use, a voltage dividing circuit is connected outside the photomultiplier 10, the voltage dividing circuit includes a resistor R20, a resistor R21, a resistor R22, a resistor R23, a resistor R24, a resistor R25, a resistor R26, a resistor R27, a resistor R28, a resistor R29 and a resistor R30 which are connected in sequence, one end of the resistor R20 far from the resistor R21 is powered by positive high voltage, a capacitor C19 is connected in parallel outside the resistor R20, a capacitor C20 is connected in parallel outside the resistor R21, a capacitor C21 is connected in parallel outside the resistor R22, and the capacitor C19, the capacitor C20 and the capacitor C21 are all filter capacitors, so that voltage drop between poles due to large pulse current is avoided, and a photomultiplier signal is coupled to an input end of the pre-amplification circuit through the capacitor C18.
It should be noted that the photomultiplier tube 10 is supplied with a positive high voltage, which has an advantage of reducing noise of the photomultiplier tube 10. The cathode is ground potential when the positive high voltage is supplied, and the anode is connected with positive polarity high voltage; in addition, when in practical use, the permalloy metal sleeve is added outside the photomultiplier tube 10 to be used as an electromagnetic shield, and the permalloy metal sleeve is also grounded. Therefore, there is no potential difference between the metal sheath and the glass envelope coated with the photocathode, and thus, no weak discharge is generated therebetween to increase the noise of the photomultiplier tube.
In this embodiment, as shown in fig. 6, the main amplifying circuit includes an operational amplifier U1, an operational amplifier U2, and an operational amplifier U3, a non-inverting input terminal of the operational amplifier U1 is divided into two paths, one path is connected to an output terminal of the pre-amplifying circuit through a capacitor C11, the other path is grounded through a resistor R14, an output terminal of the operational amplifier U1 is divided into two paths, one path is connected to an inverting input terminal of the operational amplifier U1 through a resistor R2, the other path is connected to an inverting input terminal of the operational amplifier U2 through a capacitor C12 and a resistor R11 in sequence, a positive power supply terminal of the operational amplifier U1 is connected to a +5V power supply, and a negative power supply terminal of the operational amplifier U1 is connected to a-5; the non-inverting input end of the operational amplifier U2 is grounded through a resistor R16, the output end of the operational amplifier U2 is divided into two paths, one path is connected with the inverting input end of the operational amplifier U2 through a resistor R6, the other path is connected with the non-inverting input end of the operational amplifier U3 through a resistor R12, the positive electrode of a power supply of the operational amplifier U2 is connected with a +5V power supply, and the negative electrode of the power supply of the operational amplifier U2 is grounded; the non-inverting input end of the operational amplifier U3 is grounded through a capacitor C16, the inverting input end of the operational amplifier U3 is grounded through a resistor R7, the output end of the operational amplifier U3 is divided into two paths, one path is connected with the inverting input end of the operational amplifier U3 through a resistor R8, the other path is grounded through a capacitor C13 and a resistor R15 in sequence, the connecting end of a capacitor C13 and a resistor R15 serves as the output end of the main amplifying circuit, the positive power supply electrode of the operational amplifier U3 is connected with a +5V power supply, and the negative power supply electrode of the operational amplifier U3 is grounded.
In practical use, the operational amplifier U1, the operational amplifier U2 and the operational amplifier U3 are all operational amplifiers of the type THS4281, the resistances of the resistors R1 and R10 are both 10 Ω, the resistance of the resistor R2 is 150 Ω, the resistance of the resistor R3 is 3k Ω, the resistance of the resistor R4 is 200k Ω, the resistance of the resistor R5 is 9.1k Ω, the resistance of the resistor R6 is 3.3k Ω, the resistances of the resistors R7 and R24 are both 1k Ω, the resistance of the resistor R8 is 4.7k Ω, the resistance of the resistor R8 is 22 Ω, the resistance of the resistor R8 is 820 Ω, the resistance of the resistor R8 is 200 Ω, the resistance of the resistor R8 is 30k Ω, the resistance of the resistor R8 is 47k Ω, the resistances of the resistors R8 and R8 are 20k, the resistance of the resistor R8 is 656, the resistances of the resistors R8, the resistors R8 and the resistors R8 are 500k, the resistors R8 and R8, the resistors R8 and R72 are 8 and R72, The resistance values of the resistor R27, the resistor R28 and the resistor R29 are all 510k omega, and the resistance value of the resistor R30 is 1M omega; the capacitance values of the capacitor C1, the capacitor C2, the capacitor C3 and the capacitor C17 are all 0.1 muF, the capacitance value of the capacitor C4 is 0.01 muF, the capacitance values of the capacitor C5, the capacitor C6, the capacitor C7, the capacitor C8, the capacitor C9, the capacitor C10, the capacitor C13, the capacitor C14, the capacitor C15 and the capacitor C16 are all 10 muF, the capacitance value of the capacitor C11 is 1 muF, the capacitance values of the capacitor C12 and the capacitor C18 are all 4.7nF, and the capacitance values of the capacitor C19, the capacitor C20 and the capacitor C21 are all 10 nF;
in this embodiment, the shielding cylinder 3 and the front cover 2, and the shielding cylinder 3 and the rear cover 4 are connected by hinges 13.
It should be noted that, the shielding cylinder 3 is connected with the front cover 2 and the rear cover 4 through the hinge 13, so that the installation of the gas sampling pipeline and the radiation detection assembly are convenient, the complex screw screwing operation is not needed, and the use is convenient and fast.
In this embodiment, the bottom of the shielding shell is provided with a mounting seat 14.
It should be noted that the shielding shell is easy to carry by arranging the mounting seat 14, and meanwhile, the mounting seats 14 with different shapes and functions can be designed according to different situations on site, so that the device is more convenient to use and install.
In this embodiment, a groove 15 is formed at one end of the rear cover 4 away from the hinge 13.
It should be noted that the opening and closing of the rear cover 4 is facilitated by the provision of the groove 15.
In this embodiment, the crystal 9 is a NaI scintillation crystal 50mm × 50mm, and the photomultiplier tube 10 is a CR105-03 type photomultiplier tube.
In this embodiment, the embedded source 12 is an americium source.
In this embodiment, a plug 16 is disposed on the rear cover 4, one end of the plug 16 passes through the rear cover 4 to be connected to the signal processing circuit board 11, and the other end of the plug 16 is connected to the computer through a cable.
When the utility model is used, the lead rod is firstly used for filling the source detection through hole, the rear cover 4 is opened to install the radiation detection assembly in the shielding cylinder 3, the front cover 2 is opened after the instrument is placed at the designated position, the gas sampling pipeline 1 is placed between the first through groove 5 and the second through groove 6, the front cover 2 is closed, and the instrument starts to work; the radiation detection assembly detects the gamma activity of the covering gas in the gas sampling pipeline 1, and when gamma rays radiated by the covering gas in the gas sampling pipeline 1 are incident to the NaI crystal, atoms or molecules of the crystal are excited to generate fluorescence. The average frequency of crystal scintillation is proportional to the intensity of the incident radiation, and the intensity of the single fluorescence is proportional to the energy of the incident radiation, and these fluorescences act on the photocathode of the photomultiplier tube to eject electrons therefrom. The number of the emitted electrons is continuously increased due to the secondary electron emission effect on the dynode of the photomultiplier, finally, a pulse signal is generated on the cathode load of the photomultiplier, and the negative pulse is processed by the signal processing circuit board 11 after being capacitively coupled so as to better transmit signals to a computer; the crystal 9 identifies the radiation signal sent by the embedded source 12 and converts the radiation signal into an optical signal so as to facilitate the signal conversion of a subsequent photomultiplier, the detection data of the embedded source 12 of which the output end of the photomultiplier is subjected to signal processing is used as reference data, and whether a radiation detection assembly is damaged or not is identified so as to facilitate the timely replacement and maintenance of equipment; when needing to detect radiation detection subassembly whether be in under normal operating condition, extract the lead rod, insert the device is examined to the source, and T type lead stopper 7 is kept away from the one end of radiation source 8 and is blocked outside shielding section of thick bamboo 3, prevents that T type lead stopper 7 from excessively going deep into and causing radiation source 8 to damage in shielding section of thick bamboo 3, judges according to the radioactivity of radiation source 8 that radiation detection subassembly detected whether there is the damage radiation detection subassembly to the timely change maintenance of equipment improves the holistic life of instrument.
The above, only be the utility model discloses a preferred embodiment, it is not right the utility model discloses do any restriction, all according to the utility model discloses the technical entity all still belongs to any simple modification, change and the equivalent structure change of doing above embodiment the utility model discloses technical scheme's within the scope of protection.
Claims (9)
1. A fast reactor covering gas gamma activity monitor is characterized in that: comprises a shielding shell sleeved on a gas sampling pipeline (1) and a radiation detection assembly which is arranged in the shielding shell and matched with the gas sampling pipeline (1);
the shielding shell comprises a front cover (2), a shielding cylinder (3) and a rear cover (4) which are sequentially connected, the radiation detection assembly is arranged in the shielding cylinder (3), one end, matched with the shielding cylinder (3), of the front cover (2) is provided with a first through groove (5) matched with the gas sampling pipeline (1), the shielding cylinder (3) is provided with a second through groove (6) matched with the gas sampling pipeline (1), the side wall of the shielding cylinder (3) is provided with a source detection through hole matched with the detection end of the radiation detection assembly and communicated with the inside of the shielding cylinder (3), and the source detection through hole is filled with a source detection device which comprises a T-shaped lead plug (7) and a radioactive source (8) arranged at one end, close to the inside of the shielding cylinder (3), of the T-shaped lead plug (7);
the radiation detection assembly comprises a crystal (9), a photomultiplier (10) and a signal processing circuit board (11) which are sequentially connected, an embedded source (12) is arranged at one end, matched with the gas sampling pipeline (1), of the crystal (9), a pre-amplification circuit and a main amplification circuit are integrated on the signal processing circuit board (11), and the output end of the photomultiplier (10) is connected with the input end of the pre-amplification circuit.
2. The fast reactor blanketing gas gamma activity monitor of claim 1, wherein: the preamplifier circuit comprises a capacitor C18, a PNP triode Q1 and a PNP triode Q2, wherein one end of the capacitor C18 is connected with the anode of a photomultiplier (10), the other end of the capacitor C18 is connected with the base electrode of the PNP triode Q1, the photomultiplier (10) adopts positive high voltage for power supply, the emitter electrode of the PNP triode Q1 is divided into three paths, one path is sequentially connected with a +12V power supply through a resistor R5 and a resistor R1, the second path is connected with the base electrode of the PNP triode Q2 through a resistor R9, the third path is sequentially connected with the connecting end of a resistor R5 and a resistor R1 through a capacitor C9 and a resistor R4, the connecting end of the capacitor C9 and a resistor R4 is divided into two paths, one path is grounded through a resistor R17, the other path is connected with the base electrode of the PNP triode Q1 through a resistor R13, the collector electrode of the PNP triode Q1 is divided into two paths, one path is grounded through a resistor R18, the other path is connected with, the emitting electrode of the PNP triode Q2 is divided into two paths, one path is connected with the connecting end of the resistor R5 and the resistor R1 through the resistor R3, the other path is connected with one end of the resistor R10 through the capacitor C10, and the other end of the resistor R10 is the output end of the pre-amplification circuit.
3. The fast reactor blanketing gas gamma activity monitor of claim 2, wherein: the main amplifying circuit comprises an operational amplifier U1, an operational amplifier U2 and an operational amplifier U3, wherein the non-inverting input end of the operational amplifier U1 is divided into two paths, one path is connected with the output end of the pre-amplifying circuit through a capacitor C11, the other path is grounded through a resistor R14, the output end of the operational amplifier U1 is divided into two paths, one path is connected with the inverting input end of the operational amplifier U1 through a resistor R2, the other path is sequentially connected with the inverting input end of the operational amplifier U2 through a capacitor C12 and a resistor R11, the positive electrode of a power supply of the operational amplifier U1 is connected with a +5V power supply, and the negative electrode of the power supply of the operational amplifier U1 is connected with; the non-inverting input end of the operational amplifier U2 is grounded through a resistor R16, the output end of the operational amplifier U2 is divided into two paths, one path is connected with the inverting input end of the operational amplifier U2 through a resistor R6, the other path is connected with the non-inverting input end of the operational amplifier U3 through a resistor R12, the positive electrode of the power supply of the operational amplifier U2 is connected with a +5V power supply, and the negative electrode of the power supply of the operational amplifier U2 is grounded; the non-inverting input end of the operational amplifier U3 is grounded through a capacitor C16, the inverting input end of the operational amplifier U3 is grounded through a resistor R7, the output end of the operational amplifier U3 is divided into two paths, one path is connected with the inverting input end of the operational amplifier U3 through a resistor R8, the other path is grounded through a capacitor C13 and a resistor R15 in sequence, the connecting end of a capacitor C13 and a resistor R15 serves as the output end of the main amplifying circuit, the positive electrode of a power supply of the operational amplifier U3 is connected with a +5V power supply, and the negative electrode of the power supply of the operational amplifier U3 is.
4. The fast reactor blanketing gas gamma activity monitor of claim 1, wherein: the shielding cylinder (3) and the front cover (2) and the shielding cylinder (3) and the rear cover (4) are connected through hinges (13).
5. The fast reactor blanketing gas gamma activity monitor of claim 1, wherein: and the bottom of the shielding shell is provided with a mounting seat (14).
6. The fast reactor blanketing gas gamma activity monitor according to claim 4, wherein: and a groove (15) is formed in one end, far away from the hinge (13), of the rear cover (4).
7. The fast reactor blanketing gas gamma activity monitor of claim 2, wherein: the crystal (9) is a NaI scintillation crystal with the diameter of 50mm multiplied by 50mm, and the photomultiplier (10) is a CR105-03 type photomultiplier.
8. The fast reactor blanketing gas gamma activity monitor of claim 1, wherein: the embedded source (12) is an americium source.
9. The fast reactor blanketing gas gamma activity monitor of claim 1, wherein: the rear cover (4) is provided with a plug (16), one end of the plug (16) penetrates through the rear cover (4) to be connected with the signal processing circuit board (11), and the other end of the plug (16) is connected with a computer through a cable.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN202021350288.2U CN212483883U (en) | 2020-07-10 | 2020-07-10 | Fast reactor covering gas gamma activity monitor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN202021350288.2U CN212483883U (en) | 2020-07-10 | 2020-07-10 | Fast reactor covering gas gamma activity monitor |
Publications (1)
Publication Number | Publication Date |
---|---|
CN212483883U true CN212483883U (en) | 2021-02-05 |
Family
ID=74455861
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN202021350288.2U Active CN212483883U (en) | 2020-07-10 | 2020-07-10 | Fast reactor covering gas gamma activity monitor |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN212483883U (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN113267804A (en) * | 2021-05-26 | 2021-08-17 | 西安中核核仪器有限公司 | Light-shielding detection method for liquid scintillation counter |
-
2020
- 2020-07-10 CN CN202021350288.2U patent/CN212483883U/en active Active
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN113267804A (en) * | 2021-05-26 | 2021-08-17 | 西安中核核仪器有限公司 | Light-shielding detection method for liquid scintillation counter |
CN113267804B (en) * | 2021-05-26 | 2022-02-08 | 西安中核核仪器股份有限公司 | Light-shielding detection method for liquid scintillation counter |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CN201096508Y (en) | Flash detector for material level detection | |
CN112882082B (en) | Measuring method of neutron-gamma ambient dose equivalent rate instrument based on pulse shape discrimination | |
CN106990429A (en) | A kind of γ, neutron dual-beam spectral measurement device and measuring method | |
CN212483883U (en) | Fast reactor covering gas gamma activity monitor | |
CN112213763A (en) | Gamma dose monitoring devices based on long-range wireless communication | |
CN113885069A (en) | Alpha detector and D-T neutron marking device | |
CN113109861A (en) | Radiation detection device and method thereof | |
CN112904403A (en) | Wide-energy-spectrum neutron fluence on-line monitoring system | |
CN218037366U (en) | High-precision measuring equipment for radiation monitoring | |
CN109490023A (en) | A kind of activity metering unit for the sampling of gas on-line continuous | |
CN109557575A (en) | A kind of neutron multiplicity measuring device and its application method | |
CN111596337B (en) | Tritium detection method in high radon environment based on scintillation fiber array | |
CN109493984A (en) | A kind of Nuclear Plant breakage on-line measuring device | |
CN108802792A (en) | The measuring device and method of radioactivity inert gas | |
CN210347946U (en) | Off-axis single-reflection gamma measuring system | |
CN217213181U (en) | Beta activity monitoring device for explosion-proof gas pipeline in high gamma background environment | |
CN112180419A (en) | Detection unit, detection part and detector of air tritium | |
CN115453610B (en) | Neutron full-section detector and detection method thereof | |
CN114325809B (en) | Neutron dosimeter based on current integral electronic system | |
CN113484895B (en) | Alpha surface pollution detector and detection method for high radon background | |
CN113539532B (en) | Spent fuel assembly damage detection system and method | |
CN212321861U (en) | Radioactive aerosol detection device | |
CN112731510B (en) | Mobile radioactive iodine monitoring method | |
CN214586023U (en) | Gamma dose monitoring devices based on long-range wireless communication | |
CN211263789U (en) | Pulse gating neutron detector |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
GR01 | Patent grant | ||
GR01 | Patent grant | ||
CP01 | Change in the name or title of a patent holder | ||
CP01 | Change in the name or title of a patent holder |
Address after: Yanta District in Shaanxi province Xi'an City Road 710061, No. 108 Patentee after: Xi'an Zhonghe Nuclear Instrument Co.,Ltd. Address before: Yanta District in Shaanxi province Xi'an City Road 710061, No. 108 Patentee before: XI'AN ZHONGHE NUCLEAR APPARATUS CO.,LTD. |