CN113096836B - A neutron detection system and its installation method - Google Patents
A neutron detection system and its installation method Download PDFInfo
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- CN113096836B CN113096836B CN202110342127.1A CN202110342127A CN113096836B CN 113096836 B CN113096836 B CN 113096836B CN 202110342127 A CN202110342127 A CN 202110342127A CN 113096836 B CN113096836 B CN 113096836B
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- 230000005855 radiation Effects 0.000 claims abstract description 39
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- 238000011065 in-situ storage Methods 0.000 claims description 18
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C11/00—Shielding structurally associated with the reactor
- G21C11/08—Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation
- G21C11/083—Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation consisting of one or more metallic layers
- G21C11/085—Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation consisting of one or more metallic layers consisting exclusively of several metallic layers
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
本发明公开了一种中子探测系统及其安装方法，系统包括中子探测预设单元、中子探测单元和就地辐射处理单元；中子探测预设单元包括预先设置在罐体上的慢化屏蔽体和预先埋设在屏蔽墙体中的S预埋管，以及设置在屏蔽室内的套管；套管的一端密封且位于慢化屏蔽体内，套管的另一端与S预埋管连接；中子探测单元包括中子计数管和电缆，电缆的一端通过快插接头与中子计数管连接，电缆的另一端与就地辐射处理单元连接。本发明系统结构简单，设计合理，实现方便，能够有效应用在核辐射监测中，安全可靠性高，能够在探测环境条件严酷的情况下，准确采集到中子计数率，使用效果好，便于推广使用。
The invention discloses a neutron detection system and an installation method thereof. The system includes a neutron detection preset unit, a neutron detection unit and an on-site radiation processing unit; The shielding body and the S embedded pipe pre-buried in the shielding wall, and the casing set in the shielding room; one end of the casing is sealed and located in the moderated shielding body, and the other end of the casing is connected with the S embedded pipe; The neutron detection unit includes a neutron counting tube and a cable, one end of the cable is connected with the neutron counting tube through a quick-plug connector, and the other end of the cable is connected with the local radiation processing unit. The system of the invention is simple in structure, reasonable in design, convenient in implementation, can be effectively applied in nuclear radiation monitoring, has high safety and reliability, can accurately collect the neutron count rate under severe detection environment conditions, has good use effect and is easy to popularize use.
Description
Technical Field
The invention belongs to the technical field of nuclear radiation measurement, and particularly relates to a neutron detection system and an installation method thereof.
Background
In nuclear engineering, in order to ensure personnel safety and prevent the nuclear radiation range from being expanded, a process tank body is usually sealed in a shielding chamber formed by a shielding wall body, then neutrons are required to be monitored, but the maximum gamma dose rate level in the shielding chamber can reach 192Gy/h, and meanwhile, a large amount of decay heat can be released when radioactive elements decay, so that the neutron detection environmental condition is severe, the distance between a personnel operation area and the process tank body is far, the complexity of a neutron detection system and the installation difficulty of a front-end detector are increased, namely, the front-end detector is required to be installed at the process tank body from the outside of the shielding wall body, a higher requirement is also provided for a connecting cable of the front-end detector, the cable is required to be capable of withstanding gamma irradiation with long time and high dose rate, and the installation of the front-end detector can be facilitated.
In the prior art, a neutron detection system which is simple in structure and reasonable in design and can meet the detection requirement and the installation requirement of a front-end detector is also lacked.
Disclosure of Invention
The invention aims to solve the technical problem of providing a neutron detection system aiming at the defects in the prior art, which has the advantages of simple structure, reasonable design, convenient realization, high safety and reliability, capability of being effectively applied to radiation monitoring, capability of accurately acquiring the neutron counting rate under the condition of severe detection environmental conditions, good use effect and convenience for popularization and use.
In order to solve the technical problems, the invention adopts the technical scheme that: a neutron detection system comprises a neutron detection preset unit, a neutron detection unit and an in-situ radiation processing unit; the neutron detection preset unit comprises a moderation shield body which is arranged on the tank body in advance, an S-shaped pre-buried pipe which is embedded in a shield wall body in advance, and a sleeve which is arranged in the shield chamber; one end of the sleeve is sealed and is positioned in the moderation shield body, and the other end of the sleeve is connected with one end of the S-shaped embedded pipe positioned in the shield wall body; the neutron detection unit comprises a neutron counting tube and a cable, one end of the cable is connected with the neutron counting tube through a connector, and the other end of the cable is connected with the in-situ radiation processing unit; the in-situ radiation processing unit is arranged outside the shielding wall body and in a gentle environment.
The moderation shielding body comprises a shell, a shielding cover plate is arranged at an opening of the shell, the shell and the shielding cover plate form a sealing cavity, one end of the sleeve is located in the sealing cavity and located in the sealing cavity, a first moderation layer is arranged on the outer side of the sleeve, a reflection layer is arranged on the outer side of the first moderation layer, and a second moderation layer is arranged between the reflection layer and the shell.
In the neutron detection system, the reflection layer includes a plurality of layers of metal materials, and the plurality of layers of metal materials include a first beryllium copper layer, a beryllium layer, a cadmium layer, and a second beryllium copper layer, which are layered from inside to outside.
In the neutron detection system, the junction of the sleeve and the S embedded pipe is provided with the reducer section.
In the neutron detection system, one end of the neutron counting tube, which is far away from the cable, is connected with the hemispherical end part.
In the neutron detection system, the neutron counting tube is a He-3 proportional counting tube.
In the neutron detection system, the cable is an armored cable.
In the neutron detection system, the neutron counting tube passes through the S embedded tube from the outside of the shielding wall body through the armored cable and is sent into the sleeve positioned in one end of the moderation shield body.
The neutron detection system comprises a microcontroller, a real-time clock, a memory and a communication interface, wherein the real-time clock, the memory and the communication interface are all connected with the microcontroller, the input end of the microcontroller is connected with an analog input module, a switching value input module and a digital keyboard input module, and the output end of the microcontroller is connected with an analog output module, a switching value output module, an audible and visual alarm module and a display screen.
The invention also discloses an installation method of the neutron detection system, which is used for installing the system and comprises the following steps:
step one, arranging a neutron detection preset unit;
installing a slowing shield body on a tank body, installing one end of a sleeve in the slowing shield body, and connecting the other end of the sleeve with an S embedded pipe which is embedded in a shielding wall body in advance;
step two, installing a neutron detection unit;
a neutron counting tube passes through the S embedded tube from the outside of the shielding wall body through a cable and is sent into one end of the sleeve in the moderation shield body;
step three, installing a local radiation processing unit;
installing the local radiation processing unit outside the shielding wall body in a gentle environment;
step four, connecting the neutron detection unit and the in-situ radiation processing unit;
the cable is connected to a switching value input module in the in-situ radiation processing unit.
Compared with the prior art, the invention has the following advantages:
1. the system of the invention has simple structure, reasonable design and convenient realization.
2. The invention only has a neutron counting tube and a cable in the area with high radiation dosage and high temperature in the process room, and has no electronic components. The power supply and the signal transmission between the in-situ radiation processing unit and the neutron counting tube are completed by only one low-noise armored coaxial cable, and all data acquisition, processing, storage and display functions are realized by the in-situ radiation processing unit in a gentle environment.
3. The slowing shield shell consists of an outer steel plate and an inner steel plate, and lead is poured into the shell to form a lead shielding layer, so that external gamma rays can be effectively shielded, and the influence of the external gamma rays on a neutron counting tube is inhibited; the first moderating layer can moderate fast neutrons into thermal neutrons, the thermal neutrons are reflected by the reflecting layer and then collected to the neutron counting tube, and counting measurement of the neutrons is achieved through the neutron counting tube; the reflecting layer can reflect neutron rays on the outer side surface and collect the neutron rays on the detection surface, so that the detection efficiency of neutron counting on the detection surface can be effectively improved; the second moderation layer can effectively shield neutron rays on the outer side surface and inhibit the influence of the neutron rays on the neutron counting tube on the outer side surface.
4. The semi-spherical end part is designed at the tail end of the neutron counting tube, so that friction and blockage are reduced when the neutron counting tube is fed into and pulled out of the S pre-buried tube and the sleeve, the neutron counting tube is guided and positioned, and the whole installation process is smooth.
5. The neutron counting rate acquisition system can be effectively applied to nuclear radiation monitoring, is high in safety and reliability, can accurately acquire the neutron counting rate under the condition of severe detection environmental conditions, is good in using effect, and is convenient to popularize and use.
In conclusion, the system disclosed by the invention is simple in structure, reasonable in design, convenient to implement, high in safety and reliability, good in using effect and convenient to popularize and use, can be effectively applied to nuclear radiation monitoring, and can accurately acquire the neutron counting rate under the condition of severe detection environmental conditions.
The technical solution of the present invention is further described in detail by the accompanying drawings and embodiments.
Drawings
FIG. 1 is a schematic diagram illustrating the components of a child detection preset unit according to the present invention;
FIG. 2 is a schematic structural diagram of a sub-detection unit according to the present invention;
FIG. 3 is a schematic diagram of the structure of the slowing shield of the present invention;
FIG. 4 is a functional block diagram of an in situ radiation processing unit of the present invention;
fig. 5 is a flow chart of the installation method of the present invention.
Description of reference numerals:
1-slowing the shield; 1-housing; 1-2-shielding cover plate;
1-5-first moderating layer; 1-6-a reflective layer; 1-7-a second moderating layer;
2-S pre-burying the pipe; 3, sleeving a sleeve; 4-neutron counter tube;
5-a cable; 6, quick plug; 7-a microcontroller;
8, a real-time clock; 9-a memory; 10-a communication interface;
11-analog input module; 12-a switching value input module; 13-digital keyboard input module;
14, an analog quantity output module; 15-switching value output module; 16, a sound and light alarm module;
17-a display screen; 21-a tank body; and 22, shielding the wall.
Detailed Description
As shown in fig. 1 to 2, the neutron detection system of the present invention includes a neutron detection presetting unit, a neutron detection unit, and an in-situ radiation processing unit; the neutron detection preset unit comprises a moderation shield body 1 which is arranged on the tank body 21 in advance, an S embedded pipe 2 which is embedded in a shielding wall body 22 in advance, and a sleeve 3 which is arranged in a shielding chamber; one end of the sleeve 3 is sealed and is positioned in the moderating shield body 1, and the other end of the sleeve 3 is connected with one end of the S embedded pipe 2 positioned in the shielding wall 22; the neutron detection unit comprises a neutron counting tube 4 and a cable 5, one end of the cable 5 is connected with the neutron counting tube 4 through a connector 6, and the other end of the cable 5 is connected with the in-situ radiation processing unit; the in situ radiation treatment unit is disposed outside of the shielded wall 22 in a gentle environment.
In specific implementation, in consideration of high temperature and high dose (about 192Gy/h) of a field installation environment, all electronic components need to be installed in a gentle environment outside the shielding wall 22, the neutron detection unit penetrates through the S embedded pipe 2 with the diameter DN100 and enters the process room, and the neutron counting tube 4 needs to be fed into and drawn out of the S embedded pipe 2 and the sleeve 3 in the process.
The areas with high radiation dose and high temperature in the process room are only the neutron counter tube 4 and the cable 5 without any electronic components. The power supply and signal transmission between the in-situ radiation processing unit and the neutron counting tube 4 are completed by only one low-noise armored coaxial cable 5, and all data acquisition, processing, storage and display functions are realized by the in-situ radiation processing unit in a gentle environment.
In this embodiment, as shown in fig. 3, the slowing-down shielding body 1 includes a housing 1-1, a shielding cover plate 1-2 is disposed at an opening of the housing 1-1, the housing 1-1 and the shielding cover plate 1-2 form a sealed cavity, one end of the sleeve 3 is located in the sealed cavity, a first slowing-down layer 1-5 is disposed on the outer side of the sleeve 3 located in the sealed cavity, a reflective layer 1-6 is disposed on the outer side of the first slowing-down layer 1-5, and a second slowing-down layer 1-7 is disposed between the reflective layer 1-6 and the housing 1-1.
In specific implementation, the shell 1-1 consists of an outer steel plate and an inner steel plate, and lead is poured into the shell to form a lead shielding layer, so that external gamma rays can be effectively shielded, and the influence of the external gamma rays on the neutron counting tube 4 is inhibited; the first moderating layer 1-5 can slow fast neutrons into thermal neutrons, the thermal neutrons are reflected by the reflecting layer 1-6 and then collected into the neutron counting tube 4, and counting measurement of the neutrons is realized by the neutron counting tube 4; the reflecting layers 1-6 can reflect neutron rays on the outer side surface and collect neutron rays on the detection surface, so that the detection efficiency of neutron counting on the detection surface can be effectively improved; the second slowing-down layers 1-7 can effectively shield neutron rays on the outer side surface and inhibit the influence of the neutron rays on the neutron counting tube 4 on the outer side surface. Moreover, in order to adapt to the radiation characteristics of different measuring points, the thicknesses of the first slowing-down layer 1-5, the reflection layer 1-6 and the second slowing-down layer 1-7 can be adjusted.
In this embodiment, the reflective layers 1 to 6 include multiple layers of metal materials, where the multiple layers of metal materials include a first beryllium copper layer, a beryllium layer, a cadmium layer, and a second beryllium copper layer, which are layered from inside to outside.
In specific implementation, the first beryllium copper layer is a beryllium copper plate with the thickness of 1mm, the beryllium layer is a beryllium plate with the thickness of 1mm, the cadmium layer is a cadmium plate with the thickness of 2mm, and the second beryllium copper layer is a beryllium copper plate with the thickness of 1 mm.
In this embodiment, the junction of sleeve pipe 3 and S buried pipe 2 is provided with the reducing section.
In this embodiment, one end of the neutron counting tube 4, which is far away from the cable 5, is connected with a hemispherical end.
During the concrete implementation, neutron count pipe 4 designs hemisphere tip, and the neutron count pipe 4 of being convenient for sends into in S pre-buried pipe 2 and sleeve pipe 3 and when taking out, reduces friction and card pause, is favorable to neutron count pipe 4' S direction and location, makes whole installation smooth and easy.
In this embodiment, the neutron counter tube 4 is a He-3 proportional counter tube.
During specific implementation, the gas filled in the He-3 proportional counting tube is helium gas, the helium gas is stable inert gas, the He-3 proportional counting tube is non-toxic and flame-retardant, has stable physical form and chemical composition, does not generate chemical reaction due to temperature and humidity change or irradiation, and does not generate harmful substances by reaction with substances in the environment where the He-3 proportional counting tube is located.
In this embodiment, the cable 5 is an armored cable.
In specific implementation, the neutron counting tube 4 needs to be fed into the sleeve 3 through the cable 5, so that the cable 5 needs to be rigid and adopts an armored cable.
In this embodiment, the neutron counting tube 4 passes through the S embedded tube 2 from the outside of the shielding wall 22 through the armored cable and is fed into the one end of the sleeve 3 located in the slowing shield 1.
During the concrete implementation, neutron count pipe 4 blocks when the reducing section, and the personnel of sending into can definitely feel that neutron count pipe 4 has passed through the reducing section, and neutron count pipe 4 continues to exert oneself propelling movement cable 5 again when arriving 3 terminal ends of sleeve pipe, can feel that neutron count pipe 4 pushes up 3 cecum of sleeve pipe, and the cable 5 of S pre-buried pipe 2 outside no longer shortens, and neutron count pipe 4 installs and puts in place promptly and has clear feedback.
In this embodiment, as shown in fig. 4, the local radiation processing unit includes a microcontroller 7, and a real-time clock 8, a memory 9 and a communication interface 10 which are all connected to the microcontroller 7, an input end of the microcontroller 7 is connected to an analog input module 11, a switching value input module 12 and a digital keyboard input module 13, and an output end of the microcontroller 7 is connected to an analog output module 14, a switching value output module 15, an audible and visual alarm module 16 and a display screen 17.
As shown in fig. 5, the installation method of the neutron detection system of the present invention includes the following steps:
step one, arranging a neutron detection preset unit;
installing a slowing shield body 1 on a tank body 21, installing one end of a sleeve 3 in the slowing shield body 1, and connecting the other end of the sleeve 3 with an S pre-buried pipe 2 pre-buried in a shielding wall body 22;
in specific implementation, the slowing shield 1 is directly welded on the bracket through the shell 1-1, the overall dimension is not more than 225mm multiplied by 360mm, and the weight is not more than 150 kg; by slowing down the shield 1, scattered neutrons and a gamma background are shielded to within an acceptable range for the neutron counting tube 4.
Step two, installing a neutron detection unit;
a neutron counting tube 4 is conveyed into one end of the sleeve 3 positioned in the moderation shield 1 from the outside of the shield wall 22 through the S embedded tube 2 through a cable 5;
step three, installing a local radiation processing unit;
the in-situ radiation processing unit is mounted outside the shielded wall 22 in a gentle environment;
step four, connecting the neutron detection unit and the in-situ radiation processing unit;
the cable 5 is connected to the switching value input module 12 in the in-situ radiation processing unit.
The above description is only a preferred embodiment of the present invention, and is not intended to limit the present invention, and all simple modifications, changes and equivalent structural changes made to the above embodiment according to the technical spirit of the present invention still fall within the protection scope of the technical solution of the present invention.
Claims (8)
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| CN209029117U (en) * | 2018-10-16 | 2019-06-25 | 陕西卫峰核电子有限公司 | A Containment Atmospheric Radiation 18F Detection Device |
| CN210606655U (en) * | 2019-06-17 | 2020-05-22 | 陕西卫峰核电子有限公司 | Containment high-range area radiation monitoring device |
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