CN118348586A - Radiation monitoring device and extraction column neutron radiation monitoring system - Google Patents

Abstract

The invention discloses a radiation monitoring device and an extraction column neutron radiation monitoring system, wherein the device comprises: a cannula, a probe, a pulling unit and a shielding unit. The first port and the second port of the sleeve are opposite to the process equipment to be tested in orientation, and are arranged at intervals along the vertical direction. The detection section extends along the vertical direction and is located between the first port and the second port, one end of the detection section is communicated with the first port, the other end of the detection section is communicated with the second port, and the detection section is opposite to the process equipment. The detector is accommodated in the detection section, and the shielding unit extends along the vertical direction and is positioned between the detection section and the process equipment. The pulling unit is partially accommodated in the sleeve and connected with the detector, and is used for pulling the detector to move along the central axis direction of the sleeve and enabling the detector to move out of the sleeve from the first port or the second port. The device can effectively monitor the radiation of the high-level equipment, and can conveniently detach and install the monitoring instrument.

Description

Radiation monitoring device and extraction column neutron radiation monitoring system

Technical Field

The invention belongs to the field of nuclear radiation monitoring, and particularly relates to a radiation monitoring device and an extraction column neutron radiation monitoring system comprising the same.

Background

Inside a nuclear facility there are often parts of high dose rooms containing highly radioactive process equipment, resulting in higher radiation levels in these rooms. While some of these highly radioactive process equipment require radiation detection.

When the process equipment is subjected to radiation monitoring, a radiation monitoring instrument is usually installed on a bracket or a wall body in a room, so that the radiation monitoring instrument faces the process equipment, and radiation monitoring is realized. In order to ensure the accuracy of radiation monitoring, the radiation monitoring instrument needs to be regularly overhauled, calibrated and replaced. However, due to the high radiation level in the elevated room, personnel cannot access the room dismounting device or the meter mounting location, which makes it difficult to calibrate and replace the monitoring meter in the elevated room.

Disclosure of Invention

The invention aims to solve the technical problems in the prior art, and provides a radiation monitoring device and an extraction column neutron radiation monitoring system.

According to an embodiment of the first aspect of the present invention, there is provided a radiation monitoring apparatus comprising: a cannula, a probe, a pulling unit and a shielding unit. The casing comprises a first port, a second port and a detection section, the orientation of the first port and the second port is opposite to that of the process equipment to be detected, and the first port and the second port are arranged at intervals along the vertical direction. The detection section extends along the vertical direction and is positioned between the first port and the second port, one end of the detection section is communicated with the first port, the other end of the detection section is communicated with the second port, and the detection section is opposite to the process equipment. The detector is accommodated in the detection section, the shielding unit extends along the vertical direction and is positioned between the detection section and the process equipment, and the shielding unit is used for shielding background radiation in the equipment room so that the detector can monitor target radiation of the process equipment. The traction unit is partially accommodated in the sleeve and connected with the detector, and is used for traction of the detector to move along the central axis direction of the sleeve and enabling the detector to move out of the sleeve from the first port or the second port.

Preferably, the sleeve further comprises a first arc-shaped section and a second arc-shaped section, the first arc-shaped section is located between the detection section and the first port, and one end of the detection section is communicated with the first port through the first arc-shaped section. The second arc section is located between the detection section and the second port, and the other end of the detection section is communicated with the second port through the second arc section.

Preferably, the traction unit comprises a first traction device, a second traction device and a traction rope, the first traction device is opposite to the first port, the first traction device and the first port are arranged at intervals along the first axis direction, the first axis direction is the central axis direction of the first port, the second traction device is opposite to the second port, the second traction device and the second port are arranged at intervals along the second axis direction, the second axis direction is the central axis direction of the second port, the traction rope part is arranged in the sleeve in a penetrating mode, one end part of the traction rope is connected with the first traction device, the other end part of the traction rope is connected with the second traction device, the detector is connected with the middle section of the traction rope and can move along with the traction rope, and the first traction device and the second traction device are used for being matched with the traction rope to retract and retract so as to drive the detector to move along the central axis direction of the sleeve.

Preferably, the traction unit further comprises a plurality of limit identifiers, an inductor and a controller, wherein the controller is electrically connected with the first traction device and the second traction device, and is used for controlling the first traction device and the second traction device to be matched with and retract a traction rope, so as to drive the detector to move, the limit identifiers are connected with the traction rope, the number of the limit identifiers is multiple, the limit identifiers are arranged at intervals along the extending direction of the traction rope, a plurality of monitoring points are arranged in a detection section of the sleeve, the monitoring points are arranged at intervals along the central axis of the detection section, the number of the limit identifiers is the same as the number of the monitoring points, each limit identifier corresponds to one monitoring point, the inductor is located on the outer side of the sleeve and faces the traction rope, and is used for sensing the limit identifiers, and sending a stay signal when sensing the limit identifiers, the controller is electrically connected with the inductor, and is used for driving the first detector and the second traction device to move when the stay signal is sensed, and the detector is driven to stop moving.

Preferably, the first tractor and the second tractor are both electric winches.

Preferably, the detector is a neutron detector.

Preferably, the shielding unit comprises a shielding layer and a slowing layer, the shielding layer and the slowing layer are stacked, the shielding layer is abutted to the detection section of the sleeve, and the slowing layer is located on the outer side of the shielding layer.

Preferably, the shielding layer is a lead shielding layer, and the slowing layer is a polyethylene slowing layer.

According to an embodiment of the second aspect of the present invention, there is provided an extraction column neutron radiation monitoring system, including an analysis unit and the radiation monitoring device in the embodiment of the first aspect, the extraction column extending in a vertical direction, a detection section of a sleeve of the radiation monitoring device facing the extraction column, a shielding unit located between the detection section and the extraction column, the shielding unit being configured to shield background radiation in a device room, such that a detector in the radiation monitoring device can monitor neutron radiation signals of the extraction column, the detector being electrically connected to the analysis unit for uploading neutron radiation signals of the extraction column to the analysis unit, the analysis unit being configured to obtain neutron radiation doses of the extraction column from the neutron radiation signals.

Preferably, the system further comprises a wall body, wherein the wall body is positioned between the operation room and the equipment room, the extraction column is positioned in the equipment room, the wall body is provided with a first side face and a second side face, the first side face faces the operation room, the second side face faces the equipment room, the sleeve is embedded in the wall body, a first port and a second port of the sleeve extend out of the first side face of the wall body into the operation room, and a detection section of the sleeve is positioned at the second side face of the wall body; the shielding unit is embedded on the second side surface of the wall body and is positioned outside the sleeve.

The sleeve of the radiation monitoring device is buried in the wall body, the first port and the second port of the sleeve extend out from one side face of the wall body, which is close to the operation chamber, the detection section of the sleeve is positioned at the second side face of the wall body and faces to process equipment (namely the extraction column), and the detector is accommodated in the detection section. The shielding unit is positioned between the detection section and the process equipment and is used for shielding background radiation of the equipment chamber so that the detector can monitor neutron radiation of the extraction column. The haulage rope part of traction unit wears to locate in the sleeve pipe, and traction unit's first tractor and second tractor all are in the operating chamber, can receive and release the haulage rope through first tractor and second tractor cooperation to draw the axial displacement of detector along the detection section, and then make the detector to carry out the parking monitoring when removing different appointed measurement station positions. The traction unit can also draw the detector out of the sleeve from the first port or the second port so as to facilitate overhauling or replacing the detector. Therefore, the radiation monitoring device can effectively monitor the radiation of the highly radioactive process equipment, and can conveniently detach and install the monitoring instrument.

Drawings

FIG. 1 is a schematic view of a cross-sectional structure in a vertical direction of a radiation monitoring apparatus in some embodiments of the invention;

Fig. 2 is a schematic cross-sectional view of a radiation monitoring apparatus in accordance with some embodiments of the invention.

In the figure: 1-sleeve, 11-detection section, 12-first port, 13-second port, 14-first arc section, 15-second arc section, 2-traction unit, 21-first tractor, 22-second tractor, 23-traction rope, 24-limit marker, 25-sensor, 3-detector, 31-measurement cable, 4-shielding unit, 41-shielding layer, 42-slowing layer, 5-extraction column, 6-wall, 61-first mount, 62-second mount.

Detailed Description

The following description of the embodiments of the present invention will be made more apparent, and the embodiments described in detail, but not necessarily all, in connection with the accompanying drawings. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to fall within the scope of the invention.

In the description of the present invention, it should be noted that, the terms "upper," "lower," and the like indicate an orientation or a positional relationship based on the orientation or the positional relationship shown in the drawings, and are merely for convenience and simplicity of description, and do not indicate or imply that the apparatus or element in question must be provided with a specific orientation, be configured and operated in a specific orientation, and thus should not be construed as limiting the present invention.

In the description of the present invention, the terms "first," "second," and "second" 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 should be noted that, unless explicitly specified and limited otherwise, the terms "connected," "configured," "mounted," "secured," and the like are to be construed broadly and may be either fixedly connected or detachably connected, or integrally connected, for example; can be directly connected or indirectly connected through an intermediate medium, and can be communication between two elements. The specific meaning of the above terms in the present invention can be understood by those skilled in the art according to the specific circumstances.

Example 1

Referring to fig. 1 and 2, the present invention discloses a radiation monitoring apparatus, comprising: a cannula 1, a detector 3, a pulling unit 2 and a shielding unit 4.

The casing 1 comprises a first port 12, a second port 13 and a detection section 11, the first port 12 and the second port 13 face opposite to the process equipment to be detected, and the first port 12 and the second port 13 are arranged at intervals along the vertical direction. The detection section 11 extends along the vertical direction and is positioned between the first port 12 and the second port 13, one end of the detection section 11 is communicated with the first port 12, the other end is communicated with the second port 13, and the detection section 11 is opposite to the process equipment. The detector 3 is accommodated in the detection section 11, the shielding unit 4 extends in a vertical direction and is located between the detection section 11 and the process equipment, the shielding unit 4 being used for shielding background radiation in the equipment room, so that the detector 3 can monitor target radiation of the process equipment. The pulling unit 2 is partly accommodated in the cannula 1 and connected to the probe 3 for pulling the probe 3 in the direction of the centre axis of the cannula 1 and enabling the probe 3 to be moved out of the cannula 1 from the first port 12 or the second port 13.

It should be noted that the device is a wall-embedded traction type positionable radiation monitoring device, which is suitable for all working scenes in which radiation monitoring needs to be performed on process equipment, in particular for the nuclear detection field of nuclear fuel post-treatment technology, such as working scenes in which neutron radiation monitoring is performed on an extraction column 5 in a post-treatment plant.

The use of the extraction column 5 will be described first:

inside the nuclear plant, the extraction column 5 is a common spent fuel post-treatment device, which is mainly used for the extraction process flow of separating and recovering uranium, plutonium from spent fuel. The extraction column 5 has a strong radiation, wherein neutron radiation is a common radiation type in the extraction column 5 and neutron radiation has a large influence on both equipment and staff, thus requiring real-time monitoring of the neutron radiation of the extraction column 5.

In a post-treatment facility, the extraction column 5 typically needs to be placed in a hermetically sealed equipment room (i.e., a high-rise room) to avoid radiation leakage from the extraction column 5. Currently, in neutron radiation monitoring of the extraction column 5, a monitoring instrument is usually placed in a device room and mounted on a wall or a bracket, and the monitoring instrument faces the extraction column 5 to monitor the neutron radiation intensity of the extraction column 5. However, the extraction column 5 is typically an elongated tubular device that is placed in a vertical direction. Due to the large axial length of the extraction column 5, there may be a large difference in neutron radiation at each point in the vertical axis direction of the extraction column 5, and thus neutron radiation monitoring needs to be performed at each point in the vertical direction of the extraction column 5. In this regard, it is common practice to provide a plurality of monitoring instruments arranged at intervals in the vertical direction, each corresponding to a point location, for monitoring neutron radiation signals at each point location on the extraction column 5.

However, this monitoring approach has the following problems: 1. in the post-treatment facilities, the number of extraction columns 5 is large, and one extraction column 5 requires a plurality of monitoring instruments for monitoring, which results in low economical efficiency.

2. In the aftertreatment facility, the staff gets into the isolation room and is inconvenient, and this just leads to monitoring instrument dismouting very inconvenient, and in the dismouting in-process, the staff health receives radiation damage easily.

3. In post-processing facilities, the radiation monitoring instruments need to be regularly overhauled, calibrated or replaced, however, because the monitoring instruments are arranged in a sealed and isolated equipment room, the monitoring instruments in the equipment room are difficult to calibrate or replace by staff.

In summary, the nuclear facility typically has a portion of the high dose room (e.g., the equipment room in which Gao Fanggong process equipment is located) that is exposed to high radiation levels and contains process equipment (e.g., extraction column 5) that is required for neutron radiation detection. The equipment to be monitored is far away from the wall 6 of the high-dose room, personnel cannot enter and exit the room dismounting instrument or personnel at the installation position of the instrument are difficult to approach, but the radiation monitoring instrument has the requirements of regular maintenance, calibration and replacement. The maintenance and installation of such equipment requires protection of personnel radiation safety, and shielding of monitoring environmental background effects to ensure detection accuracy.

In this regard, the present embodiment proposes a radiation monitoring apparatus to solve the above-mentioned problems. The radiation monitoring device is wall-embedded traction type positionable neutron radiation monitoring equipment and is used for neutron radiation monitoring of process equipment at a wall-leaning position in a high-dose room. Specifically, in the post-treatment facility, the sleeve 1 of the radiation monitoring apparatus is buried in the wall 6, and the wall 6 is located between the equipment room and the operation room for partitioning the equipment room and the operation room. The equipment room is a high-level room, and the operation room is a low-level room. The wall 6 has a first side facing the operating room and a second side facing the operating room. The first port 12 and the second port 13 of the sleeve 1 extend from the first side of the wall 6 into the operating room for the operator to operate the detector 3 inside the sleeve 1. The detection section 11 of the sleeve 1 is located on the second side of the wall 6 and is directed towards the process equipment, i.e. the extraction column 5.

In other words, the first port 12 and the second port 13 of the sleeve 1 face away from the process equipment to be tested, while the detection section 11 faces the process equipment, which has the advantage that the detector 3 located in the detection section 11 of the sleeve 1 can monitor the neutron radiation of the process equipment (extraction column 5), and can prevent the radioactive aerosols generated by the process equipment (i.e. the extraction column 5) from leaking to the outside through the ports of the sleeve 1.

The detection section 11 of the sleeve 1 extends in the vertical direction with its upper end flush with the upper end of the extraction column 5 in the horizontal direction and its lower end flush with the lower end of the extraction column 5 in the horizontal direction.

Further, the sleeve 1 further comprises a first arc-shaped section 14 and a second arc-shaped section 15, wherein the first arc-shaped section 14 is positioned between the detection section 11 and the first port 12, and one end of the detection section 11 is communicated with the first port 12 through the first arc-shaped section 14. The second arc-shaped section 15 is located between the detection section 11 and the second port 13, and the other end of the detection section 11 is communicated with the second port 13 through the second arc-shaped section 15. In other words, the first arc-shaped section 14, the detection section 11 and the second arc-shaped section 15 of the sleeve 1 are sequentially communicated, so that a passage for the movement of the probe 3 is formed inside thereof. The probe 3 can be pulled to move within the casing 1 by the pulling unit 2. In particular, this has the advantage that the detector 3 can be pulled into the tube 1 by the pulling unit 2 to move, which enables the detector 3 to be pulled into a set measuring point position in the tube (detection section 11), and that the detector 3 can be subjected to parking monitoring when moving into different specified measuring point positions, so that neutron radiation monitoring can be performed for each target point of the extraction column 5.

Further, the traction unit 2 includes a first tractor 21, a second tractor 22, and a traction rope 23. The first tractor 21 is just to first port 12, and first tractor 21 and first port 12 are along first axis direction interval setting, and first axis direction is the central axis direction of first port 12 promptly, and the second tractor 22 is just to second port 13, and second tractor 22 and second port 13 are along the interval setting of second axis direction, and the second axis direction is the central axial direction of second port 13 promptly.

As shown in fig. 1, the first retractor 21 and the second retractor 22 are both located within the operating chamber. Specifically, the first mounting portion 61 and the second mounting portion 62 are provided in the operation chamber, the first mounting portion 61 and the second mounting portion 62 extend in the horizontal direction, and the first mounting portion 61 and the second mounting portion 62 are provided at intervals in the vertical direction. The first mounting portion 61 is located below the first port 12 and is connected to the first side of the wall 6, and the second mounting portion 62 is located below the second port 13 and is connected to the first side of the wall 6. The first retractor 21 is mounted to the first mounting portion 61, and the second retractor 22 is mounted to the second mounting portion 62.

The haulage rope 23 part wears to locate in the sleeve pipe 1, and the one end tip and the first tractor 21 of haulage rope 23 are connected, and the other end tip is connected with the second tractor 22, and the detector 3 is connected with the middle section of haulage rope 23, can remove along with haulage rope 23, and first tractor 21 and second tractor 22 are used for the cooperation to receive and release haulage rope 23 to draw the detector 3 to remove along the central axis direction of sleeve pipe 1. In particular, the probe 3 is bound to the hauling rope 23.

In the present embodiment, the first retractor 21 and the second retractor 22 are each an electric winch driven by a motor. Illustratively, the first retractor 21 includes a first motor and a first winch, and the second retractor 22 includes a second motor and a second winch. The first motor of the first retractor 21 rotates the first capstan in a first rotational direction, thereby retracting the hauling cable 23; meanwhile, the second motor of the second tractor 22 drives the second capstan to rotate in a second rotation direction, and the second rotation direction is opposite to the first rotation direction (for example, the first rotation direction is a clockwise rotation direction, and the second rotation direction is a counterclockwise rotation direction), so that the traction rope 23 is paid out. Under the cooperation of the first tractor 21 and the second tractor 22, the detector 3 moves upward in the axial direction of the detection section 11. When the detector 3 reaches the target measuring point position, the motors of the first tractor 21 and the second tractor 22 stop rotating, so that the detector 3 is kept at the target measuring point position, and at the moment, the detector 3 monitors the corresponding point position of the extraction column 5.

The detector 3 is pulled to move through the first tractor 21, the second tractor 22 and the traction rope 23, and the detector has the advantages that the detector 3 can be controlled to move back and forth along the axial direction of the detection section 11 so as to be positioned on any monitoring point, and the monitoring of all the points of the extraction column 5 can be realized through one detector 3 without arranging a plurality of detectors 3, so that the cost is greatly saved. Further, by means of the first and second retractors 21 and 22, the probe 3 can also be brought out of the cannula 1 from the first port 12 or the second port 13, whereby the probe 3 can be easily calibrated or replaced.

As shown in fig. 1, in the present embodiment, the traction unit 2 further includes a limit marker 24, an inductor 25, and a controller.

The controller is electrically connected with the first tractor 21 and the second tractor 22 and is used for controlling the first tractor 21 and the second tractor 22 to cooperatively retract and release the traction rope 23 so as to drive the detector 3 to move. The spacing identification pieces 24 are connected with the haulage rope 23, and the quantity of spacing identification pieces 24 is a plurality of, and a plurality of spacing identification pieces 24 are arranged at intervals along the extending direction of the haulage rope 23. Further, a plurality of monitoring points are arranged in the detection section 11 of the sleeve 1, and the plurality of monitoring points are arranged at intervals along the vertical direction. The number of the limit markers 24 is the same as the number of the monitoring points, and each limit marker 24 corresponds to one monitoring point. Each monitoring point corresponds to a horizontal point of the extraction column 5, and the detector 3 can stay at each monitoring point in sequence when moving along the axis direction of the detection section 11, so as to monitor neutron radiation at each horizontal point of the extraction column 5.

Further, an inductor 25 is located outside the sleeve 1 and towards the traction rope 23 for sensing the limit markers 24 and emitting a stay signal when sensing the limit markers 24. The controller is electrically connected with the sensor 25 and is used for controlling the first tractor 21 and the second tractor 22 to stop driving the detector 3 to move when the stay signal is received, so that the detector 3 stays at each monitoring point and is monitored.

As shown in fig. 1, the inductor 25 is mounted on the wall 6 above the first port 12, and the inductor 25 faces the portion of the traction rope 23 between the first tractor 21 and the first port 12 of the casing 1. The limit markers 24 are arranged at the lower end of the traction rope 23, and the sensor 25 is used for identifying the limit markers 24 on the traction rope 23 at the part between the first tractor 21 and the first port 12 of the sleeve 1, and it is easy to understand that the sensor 25 identifies one limit marker 24 at a time so as to avoid the positioning error of the current position of the detector 3.

Of course, the sensor 25 may be mounted in other locations as long as the requirement of scanning one limit marker 24 at a time is met. Illustratively, the inductor 25 may be mounted on the aforementioned first mounting portion 61 and located between the first retractor 21 and the first port 12. In addition, the limit marker 24 may be provided at the upper end portion of the traction rope 23, and in this case, the sensor 25 may be mounted on the wall 6 above the second port 13, or the sensor 25 may be mounted on the second mounting portion 62 and located between the second retractor 22 and the second port 13. At this point, the inductor 25 is directed towards the portion of the pull string 23 between the second retractor 22 and the second port 13 of the cannula 1.

The positioning principle of the traction component of the radiation monitoring device is specifically described as follows:

First, the controller controls the winch of the first retractor 21 to pay out the hauling rope 23, and the winch of the second retractor 22 is rotated in cooperation to retract the hauling rope 23. The lower half section of the traction rope 23 is provided with a plurality of limit markers 24 at intervals, when the winch of the second tractor 22 withdraws the traction rope 23, the limit markers 24 are sequentially moved out of the second port 13, and the sensor 25 sequentially senses the limit markers 24. At the same time, the detector 3 is moved downwards in the axial extension of the detection section 11. Whenever the sensor 25 senses a limit marker 24, the first retractor 21 and the second retractor 22 are controlled to stop rotating so that the detector 3 can stay at each monitoring point and monitor the neutron radiation dose of the extraction column 5.

In this embodiment, the limit markers 24 and the sensor 25 may be any existing sensing and identifying device. For example: two-dimensional code tags and infrared scanners, or RFID tags and RFID readers (i.e., radio frequency identification systems), and so forth.

In the present embodiment, the detector 3 is a neutron detector 3. The neutron detector 3 comprises electronics such as a detection gas and a fill gas, an integrated preamplifier. The neutron detector 3 may be implemented by existing equipment, and will not be described in detail herein.

In addition, referring to fig. 1 and 2, in the present embodiment, the shielding unit 4 of the radiation monitoring unit is embedded on the second side of the wall 6, and the shielding unit 4 is used for shielding background radiation in the equipment room, so that the detector 3 can monitor the target radiation (i.e. neutron radiation) of the process equipment (i.e. the extraction column 5).

Specifically, as shown in fig. 1, the shielding unit 4 includes a shielding layer 41 and a slowing layer 42, the shielding layer 41 and the slowing layer 42 are overlapped, the shielding layer 41 abuts against the detection section 11 of the sleeve 1, and the slowing layer 42 is located outside the shielding layer 41. Preferably, the shielding layer 41 is a lead shielding layer 41 and the moderating layer 42 is a polyethylene moderating layer. The lead shield 41 is used to shield background gamma rays. Due to the poor forces between neutrons and lead nuclei, neutrons pass through lead with little obstruction, i.e. the lead shield 41 is able to shield off background gamma rays in the equipment room while ensuring neutron radiation can pass through. And the polyethylene moderating layer 42 is used to moderate fast neutrons to increase the probability of interaction between neutrons and the detector 3. Since neutrons are neutral particles, their energy is very difficult to detect directly by the detector 3 at high energies, because the probability of interactions between neutrons and matter is low. By moderating neutrons, i.e. reducing their energy, the scattering and absorption between neutrons and the substance can be increased, thereby increasing the probability of interactions between neutron radiation and the detector 3.

The radiation monitoring apparatus will be described in more detail below, the apparatus comprising: the detector 3, the arc-shaped sleeve and the fixed sleeve (namely the arc-shaped section and the detection section 11 of the sleeve 1), the tractor (the first tractor 21 and the second tractor 22), the traction rope 23, the limiter, the measuring cable 31, the lead shielding layer 41 and the polyethylene slowing body (namely the shielding unit 4).

The arc-shaped sleeve (namely the first arc-shaped section 14 and the second arc-shaped section 15 of the sleeve 1) and the fixed sleeve (namely the detection section 11 of the sleeve 1) are both stainless steel sleeve 1 structures and are fixed in the concrete wall 6. Further, the arc-shaped sleeve and the fixed sleeve can provide a moving path of the detector 3, and the pipeline is completely embedded in the inner side of the wall 6 and does not occupy the installation space in a high-dose room. The probe 3 is sized to allow it to slide freely within the arced sleeve 1 and the fixed sleeve 1.

The retractor has a motor structure (i.e., an electric winch driven by a motor), and the hauling cable 23 has a stainless steel rope structure. The retractor provides the motive force that the detector 3 transports within the pipeline. The haulage rope 23 is arranged in the pipeline in a penetrating way in advance, the detector 3 is fixed on the haulage rope 23 head and tail when the detector 3 is installed, and the matched measuring cable 31 of the detector 3 is bound with the haulage rope 23. The tractor can be remotely controlled in the control center, and the tractor is matched with a limiter on the traction rope 23 to draw the detector 3 to a set measuring point position in the pipeline. When the detector 3 or the measuring cable 31 is replaced, the detector 3 is pulled out of the pipeline through the traction rope 23 for replacement. The measuring cable 31 has certain tensile structural strength and irradiation resistance, but the measuring cable 31 is not stressed, and the tensile power is completely provided by the traction rope 23 in the pipeline.

Before the detector 3 is installed, limiters (namely, a limit identifier 24 and an inductor 25) are installed at different positions of the hauling rope 23 according to the positions of the measuring points, the limiters are used for controlling the hauling device, and parking monitoring is carried out when the detector 3 moves to different specified measuring point positions.

It should be further noted that, the lead shielding layer 41 and the polyethylene moderating layer (i.e. the shielding unit 4) provide shielding to the background gamma rays and moderating effect to the neutrons to be detected, and the lead shielding layer 41 and the polyethylene moderating layer structure are also pre-buried in the wall 6, specifically, the second side of the wall 6.

The working principle of the radiation monitoring device is as follows:

The sleeve 1 of the radiation monitoring device is buried in the wall body 6, and the first port 12 and the second port 13 of the sleeve 1 extend out from the side face of the wall body 6, which is close to the operation room. The detection section 11 of the sleeve 1 is at the second side of the wall 6 and is directed towards the process equipment, i.e. the extraction column 5, and the detector 3 is accommodated in the detection section 11. The hauling cable 23 part of the hauling unit 2 is worn in the sleeve 1, and the first hauling device 21 and the second hauling device 22 of the hauling unit 2 are both in the operation room, and the first hauling device 21 is just over against the first port 12, and the second hauling device 22 is just against through the first hauling device 21 and the second hauling device 22 can be cooperated to receive and release the hauling cable 23, so as to draw the detector 3 to move along the axial direction of the detecting section 11, and then make the detector 3 to carry out parking monitoring when moving to different appointed measuring point positions. A shielding unit 4 is located between the detection section 11 and the process equipment for shielding background radiation of the equipment room so that the detector 3 can monitor neutron radiation of the extraction column 5.

Specifically, the controller of the traction unit 2 controls the winch of the first tractor 21 to pay out the traction rope 23, and the winch of the second tractor 22 rotates in cooperation to retract the traction rope 23. The lower half section of the traction rope 23 is provided with a plurality of limit markers 24 at intervals, when the winch of the second tractor 22 withdraws the traction rope 23, the limit markers 24 are sequentially moved out of the second port 13, and the sensor 25 sequentially senses the limit markers 24. At the same time, the detector 3 is moved downwards in the axial extension of the detection section 11. Whenever the sensor 25 senses a limit marker 24, the first retractor 21 and the second retractor 22 are controlled to stop rotating so that the detector 3 can stay at each monitoring point and monitor the neutron radiation dose of the extraction column 5.

Furthermore, when the detector 3 needs to be calibrated or replaced, the traction unit 2 can also traction the detector 3 out of the sleeve 1 through the first port 12 or the second port 13, so as to facilitate maintenance calibration or replacement of the detector 3. Therefore, the radiation monitoring device can effectively monitor the radiation of the highly radioactive process equipment, and can conveniently detach and install the monitoring instrument.

In summary, the radiation monitoring device has the following advantages:

1. only one detector 3 is needed to monitor neutron radiation dose of each point of the extraction column 5, so that the method has higher economical efficiency;

2. under the condition of ensuring the detection function and efficiency of the detector 3, the convenience of on-site installation and maintenance of the neutron detector 3 is increased, and the possibility of radioactive aerosol leakage is reduced;

3. The accuracy of the installation position of the detector 3 is improved, and the space in a room is saved;

4. the use of shielding materials such as lead is reduced, and the cost is further saved;

5. No personnel need to enter the equipment room, reducing the radiation dose to which the personnel service the detector 3 may be subjected.

Example 2

The invention also discloses an extraction column 5 neutron radiation monitoring system which comprises an analysis unit and the radiation monitoring device in the embodiment 1.

The extraction column 5 extends along the vertical direction, the detection section 11 of the sleeve 1 of the radiation monitoring device faces the extraction column 5, the shielding unit 4 is located between the detection section 11 and the extraction column 5, the shielding unit 4 is used for shielding background radiation in a device room, the detector 3 in the radiation monitoring device can monitor neutron radiation signals of the extraction column 5, the detector 3 is electrically connected with the analysis unit and used for uploading the neutron radiation signals of the extraction column 5 to the analysis unit, and the analysis unit is used for obtaining neutron radiation doses of the extraction column 5 according to neutron radiation signal analysis.

It should be noted that, this radiation monitoring device is a wall-embedded pull type locatable neutron radiation monitoring equipment, includes: the detector 3, the arc sleeve (namely the arc section of the sleeve 1) and the fixed sleeve (namely the detection section 11 of the sleeve 1), the tractor and the traction rope 23, the limiter, the measuring cable 31, the lead shielding layer 41 and the polyethylene slowing body. The detector 3 is electrically connected to the analysis unit by means of a measurement cable 31.

Further, the system further comprises a wall body 6, the wall body 6 is positioned between the operation room and the equipment room, the extraction column 5 is positioned in the equipment room, the wall body 6 is provided with a first side face and a second side face, the first side face faces the operation room, the second side face faces the equipment room, the sleeve 1 is buried in the wall body 6, a first port 12 and a second port 13 of the sleeve 1 extend out of the first side face of the wall body 6 into the operation room, and a detection section 11 of the sleeve 1 is positioned at the second side face of the wall body 6. The shielding unit 4 is embedded on the second side surface of the wall body 6 and is positioned outside the sleeve 1.

As shown in fig. 1, fig. 1 shows an arrangement mode of the radiation monitoring device, a fixed arc-shaped sleeve (namely, an arc-shaped section of the sleeve 1) and a fixed sleeve (namely, a detection section 11 of the sleeve 1) are arranged in the wall 6, a plurality of detectors 3 and cables are placed into the sleeve 1 through a tractor and a traction rope 23, and the placement position is determined through a limiter. A lead shield 41 and a polyethylene moderator are arranged in the detector 3 and the device to be detected (extraction column 5). As shown in fig. 2, fig. 2 shows the relative positions of the detector 3 and the fixture sleeve 1, lead shield 41 and polyethylene moderator, detected device in longitudinal section.

The radiation monitoring device in the embodiment 1 is adopted in the extraction column 5 neutron radiation monitoring system, so that convenience in on-site installation and maintenance of the neutron detector 3 can be improved under the condition that the detection function and the detection efficiency of the detector 3 are guaranteed, and the accuracy of the installation position of the detector 3 is improved; the use of shielding materials such as lead and structural materials such as a detector 3 bracket is reduced, the space in a room of a post-treatment factory is saved, and the material cost is reduced; the likelihood of radioactive aerosol leakage and the radiation dose to which the personnel servicing detector 3 may be subjected may also be reduced.

It is to be understood that the above embodiments are merely illustrative of the application of the principles of the present invention, but not in limitation thereof. Various modifications and improvements may be made by those skilled in the art without departing from the spirit and substance of the invention, and are also considered to be within the scope of the invention.

Claims (10)

1. A radiation monitoring apparatus, comprising: the device comprises a sleeve (1), a detector (3), a traction unit (2) and a shielding unit (4);

The casing (1) comprises a first port (12), a second port (13) and a detection section (11), wherein the first port (12) and the second port (13) are opposite to process equipment to be detected in orientation, and the first port (12) and the second port (13) are arranged at intervals along the vertical direction;

The detection section (11) extends along the vertical direction and is positioned between a first port (12) and a second port (13), one end of the detection section (11) is communicated with the first port (12), the other end of the detection section is communicated with the second port (13), and the detection section (11) is opposite to the process equipment;

The detector (3) is accommodated in the detection section (11), the shielding unit (4) extends along the vertical direction and is positioned between the detection section (11) and the process equipment, and the shielding unit (4) is used for shielding background radiation in the equipment room, so that the detector (3) can monitor target radiation of the process equipment;

The traction unit (2) is partially accommodated in the sleeve (1) and connected with the detector (3), and is used for traction of the detector (3) to move along the central axis direction of the sleeve (1) and enabling the detector (3) to be moved out of the sleeve (1) through the first port (12) or the second port (13).

2. The device according to claim 1, wherein the cannula (1) further comprises a first arcuate section (14) and a second arcuate section (15), the first arcuate section (14) being located between the detection section (11) and the first port (12), one end of the detection section (11) being in communication with the first port (12) through the first arcuate section (14);

the second arc-shaped section (15) is located between the detection section (11) and the second port (13), and the other end of the detection section (11) is communicated with the second port (13) through the second arc-shaped section (15).

3. Device according to claim 1, characterized in that the traction unit (2) comprises a first tractor (21), a second tractor (22) and a traction rope (23),

The first tractor (21) is opposite to the first port (12), the first tractor (21) and the first port (12) are arranged at intervals along a first axis direction, namely the central axis direction of the first port (12), the second tractor (22) is opposite to the second port (13), the second tractor (22) and the second port (13) are arranged at intervals along a second axis direction, namely the central axis direction of the second port (13),

The hauling cable (23) is partially arranged in the sleeve (1) in a penetrating way, one end part of the hauling cable (23) is connected with the first tractor (21), the other end part of the hauling cable is connected with the second tractor (22), the detector (3) is connected with the middle section of the hauling cable (23) and can move along with the hauling cable (23),

The first tractor (21) and the second tractor (22) are used for being matched with a drawing rope (23) to draw the detector (3) to move along the central axis direction of the sleeve (1).

4. The device according to claim 3, wherein the traction unit (2) further comprises a limit marker (24), an inductor (25) and a controller,

The controller is electrically connected with the first tractor (21) and the second tractor (22) and is used for controlling the first tractor (21) and the second tractor (22) to be matched with each other to retract and release the traction rope (23) so as to drive the detector (3) to move,

The limiting identification pieces (24) are connected with the traction rope (23), the number of the limiting identification pieces (24) is multiple, the limiting identification pieces (24) are arranged at intervals along the extending direction of the traction rope (23),

A plurality of monitoring points are arranged in the detection section (11) of the sleeve (1), the plurality of monitoring points are arranged at intervals along the central axis of the detection section (11), the number of the limit identifiers (24) is the same as that of the monitoring points, each limit identifier (24) corresponds to one monitoring point,

The sensor (25) is located the outside of sleeve pipe (1), and towards haulage rope (23), is used for the response spacing sign piece (24), and when sensing spacing sign piece (24) sends stop signal, the controller with inductor (25) electricity is connected, is used for when receiving stop signal, control first tractor (21) and second tractor (22) stop driving detector (3) and remove, make detector (3) stop and monitor in monitoring point position department.

5. The device according to claim 3 or 4, characterized in that the first retractor (21) and the second retractor (22) are both electric winches.

6. The apparatus according to claim 1, characterized in that the detector (3) is a neutron detector (3).

7. The device according to claim 1, characterized in that the shielding unit (4) comprises a shielding layer (41) and a slowing layer (42), the shielding layer (41) and the slowing layer (42) being arranged in superposition, the shielding layer (41) being against the detection section (11) of the cannula (1), the slowing layer (42) being outside the shielding layer (41).

8. The device according to claim 7, characterized in that the shielding layer (41) is a lead shielding layer (41) and the moderating layer (42) is a polyethylene moderating layer.

9. An extraction column neutron radiation monitoring system comprising an analysis unit and a radiation monitoring device according to any one of claims 1-8,

The extraction column (5) extends along the vertical direction, a detection section (11) of a sleeve (1) of the radiation monitoring device faces the extraction column (5), the shielding unit (4) is positioned between the detection section (11) and the extraction column (5), the shielding unit (4) is used for shielding background radiation in a device room, so that a detector (3) in the radiation monitoring device can monitor neutron radiation signals of the extraction column (5),

The detector (3) is electrically connected with the analysis unit and is used for uploading neutron radiation signals of the extraction column (5) to the analysis unit, and the analysis unit is used for obtaining neutron radiation doses of the extraction column (5) according to neutron radiation signals.

10. The system according to claim 9, further comprising a wall (6), the wall (6) being located between the process chamber and the equipment chamber, the extraction column (5) being located within the equipment chamber, the wall (6) having a first side and a second side, the first side facing the process chamber and the second side facing the equipment chamber,

The casing (1) is buried in the wall body (6), a first port (12) and a second port (13) of the casing (1) extend out of the first side surface of the wall body (6) into the operation chamber, and a detection section (11) of the casing (1) is positioned at the second side surface of the wall body (6);

The shielding unit (4) is embedded on the second side surface of the wall body (6) and is positioned outside the sleeve (1).