Device and method for measuring site dose rate

Abstract

The invention relates to the technical field of nuclear, and discloses a site dose rate measuring device and method. According to the site dose rate measuring device provided by the invention, a physical barrier is constructed through the sleeve pre-embedded in the outer wall of the structure and the closed blind end of the sleeve, a high-dose site is isolated from an external overhaul site, and during measurement, a probe of a monitor only needs to be inserted from the outside through a measuring channel opened by a shielding compensation structure; a worker does not need to carry equipment to enter or get close to a high-dose place, temporary perforation is not needed during measurement, and aerosol disturbance, equipment surface contamination diffusion (cross contamination) and direct external irradiation and internal irradiation risks borne by the worker which are possibly caused by the fact that the worker enters the place during operation are completely eradicated. Meanwhile, as the blind end extends into the high-dose place, the detector completely penetrates through the structural wall body, the radiation field of the place to be detected is directly detected, the dose rate of the real place which is not additionally attenuated by the wall body is measured, and the data is more accurate.

Description

Technical Field

[0001] This invention relates to the field of nuclear technology, and more specifically to a site dose rate measurement device and method. Background Technology

[0002] During the operation of nuclear facilities, the external walls of high-radiation-dose areas (such as process equipment rooms or waste storage tanks) serve as the second line of defense for radiation safety. These areas typically house radioactive process piping, equipment, and storage tanks. Due to corrosion, wear, and aging caused by intense radiation during long-term operation, the equipment and fittings within these areas require regular maintenance or replacement. However, the radiation levels inside these areas are usually extremely high, and personnel cannot enter arbitrarily. Maintenance work can only be carried out after a prior assessment and confirmation that the radiation exposure received upon entry is controlled within safe levels.

[0003] Currently, the common radiation assessment method before entering high-dose areas is as follows: First, the area is initially cleaned and decontaminated. Then, personnel use a portable long-pole gamma dose rate meter and a portable aerosol sampler, inserted through pre-installed washout holes, to measure the gamma dose rate and aerosol radioactivity concentration. Based on the measurement results, a safety assessment is conducted, and personnel entry is only approved after confirming that the radiation protection requirements for personnel entry are met.

[0004] However, based on the principles of radiation protection—the legitimacy of radiation practices, optimization of radiation protection, and personal dose equivalent limits—when using a portable long-rod gamma meter to measure the site dose rate in a high-dose area through a washout hole, even though the high-dose area is continuously ventilated to maintain a negative pressure environment, deterministic and stochastic effects may still occur, causing contamination diffusion and cross-contamination, and posing internal and external radiation risks to the workers performing the measurement work. Therefore, it is difficult to fully meet the requirements of radiation protection. Summary of the Invention

[0005] This invention provides a site dose rate measurement device and method to solve the problem that the traditional site dose rate detection process is prone to cross-contamination, resulting in failure to meet radiation protection requirements.

[0006] In a first aspect, the present invention provides a site dose rate measurement device, installed on the structural outer wall of a high-dose site in a nuclear facility, comprising a monitor and a measurement interface assembly. The monitor is equipped with a probe; the measurement interface assembly is embedded in the structural outer wall, the measurement interface assembly comprising a sleeve and a shielding compensation structure, the sleeve penetrating the structural outer wall, one end of the sleeve extending into the high-dose site having a closed blind end, and the end near the maintenance area having an open end, a measurement channel being provided between the open end and the blind end along the axis of the sleeve; the shielding compensation structure is disposed on the structural outer wall and covers the open end of the sleeve, the shielding compensation structure being used to open or close the measurement channel, the shielding compensation structure being used to compensate for the shielding effect lost due to the sleeve penetrating the structural outer wall when the measurement channel is closed, maintaining the radiation shielding integrity of the structural outer wall; wherein, when the measurement channel is open, the probe of the monitor can be inserted into the sleeve through this channel and moved to the blind end to measure the dose rate of the high-dose site.

[0007] Beneficial effects: By pre-embedded sleeves and their sealed blind ends in the external wall of the structure, a physical barrier is constructed, isolating high-dose areas from external maintenance areas. During measurement, the probe of the monitoring instrument only needs to be inserted from the outside through the measurement channel opened by the shielding compensation structure. There is no need for personnel to bring equipment into or near the high-dose area, nor is there a need for temporary perforation during measurement. This eliminates the risks of aerosol disturbance, equipment surface contamination diffusion (cross-contamination), and direct external and internal radiation exposure to workers that may occur due to personnel entering the area. Simultaneously, because the blind end extends into the high-dose area, its detector completely penetrates the structural wall, directly detecting the radiation field of the area under test and measuring the true dose rate of the area without additional attenuation by the wall, resulting in more accurate data.

[0008] In one optional embodiment, the shielding compensation structure includes a detachably connected inner shielding block and an outer shielding block, wherein the inner shielding block is installed on the outer wall of the structure, and the outer shielding block is installed on the side of the inner shielding block closer to the maintenance site.

[0009] Beneficial Effects: By including a fixed inner shielding block and a removable outer shielding block in the shielding compensation structure, the inner shielding block serves as a basic shielding and sealing layer integrated with the structural exterior wall, providing primary and stable shielding protection during long-term non-measurement periods. The outer shielding block, as an operable movable structure, is used to open or close the measurement channel as needed. This simplifies the operation of opening the measurement channel to a standard mechanical disassembly and assembly task, requiring no special tools or complex procedures, significantly improving operational efficiency. Specifically, when measurement is required, only the outer shielding block needs to be removed, while the inner shielding block remains in place, minimizing the opening time and exposed area. When closing, the two shielding blocks are installed sequentially, achieving accurate and reliable compensation for the shielding capacity at the penetration point.

[0010] In one alternative embodiment, the shielding compensation structure further includes a fastening mechanism for pressing and fixing the outer shielding block onto the inner shielding block.

[0011] Beneficial effects: By applying a clamping force to the outer shielding block through a dedicated fastening mechanism, the microscopic gaps at the interface between the outer and inner shielding blocks can be actively eliminated, ensuring that the two shielding blocks function as a whole. This effectively compensates for the weakening of interface shielding that may be introduced by the split structure, and eliminates the risk of radiation short circuit leakage from a mechanical perspective.

[0012] In one alternative embodiment, the fastening mechanism includes a handle and a clamping structure, the clamping structure being linked with the handle to open or close the outer shielding block.

[0013] Beneficial effects: By using a clamping structure linked to the handle, the force applied by rotating or turning the handle is amplified and oriented into a strong clamping force perpendicular to the bonding surface through the mechanical principle of the clamping structure, which can ensure that the entire contact interface between the inner and outer shielding blocks achieves a tight fit.

[0014] In one alternative embodiment, one end of the outer shielding block is hinged to one end of the inner shielding block.

[0015] Beneficial effects: By hinged one end of the outer shielding block to the inner shielding block, the movement trajectory of the outer shielding block is constrained, so that it can only be opened or closed along a predetermined trajectory. This avoids the risk of the shielding block slipping, tipping or bumping during disassembly, transportation and placement, and eliminates major safety hazards such as personal injury, equipment damage or pollution spread caused by accidental falling of parts.

[0016] In one alternative embodiment, a seal is provided between the inner shielding block and the open end of the sleeve.

[0017] Beneficial effects: By setting a seal between the open end of the sleeve and the inner shielding block, a static sealing interface is formed, blocking the leakage path of gas and particles, preventing gas or aerosol leakage from the gaps generated when the sleeve is installed with the wall, and helping to maintain a negative pressure environment in high-dose areas.

[0018] In one alternative implementation, the inner shielding block is fixed to the outer wall of the structure by anchors.

[0019] Beneficial effects: The inner shielding block, as the core component that bears external operating forces (such as the clamping force of the fastening mechanism and the hinge force of the opening and closing of the outer shielding block) and maintains its own shielding integrity, is rigidly connected to the sturdy structural exterior wall through anchors (such as high-strength chemical anchors and prestressed through bolts), forming a stable force transmission path. This allows the load to be effectively transmitted and distributed to the structural exterior wall through the anchors, preventing the inner shielding block from loosening or shifting.

[0020] In one alternative implementation, the blind end is used for a sealed connection with a steel cladding in a high-dose environment.

[0021] Beneficial effects: By sealing the blind end of the sleeve with the steel cladding in high-dose areas, an airtight isolation barrier is formed, preventing radioactive gases or aerosols from leaking into the wall material or behind it through the construction gap between the outer wall of the sleeve and the pre-embedded holes in the outer wall of the structure.

[0022] Secondly, the present invention also provides a site dose rate measurement method, which uses the site dose rate measurement device provided in the first aspect, and includes an operation process, which includes the following steps: when measurement is required, operation is performed on the side of the maintenance site to open the shielding compensation structure of the measurement interface component and expose the measurement channel of the sleeve; the probe of the monitor is inserted into the sleeve through the measurement channel until its measurement end reaches or approaches the blind end of the sleeve; the site dose rate in the high-dose site is measured by the monitor and the measurement data is obtained; after the measurement is completed, the probe is removed, the shielding compensation structure is closed, and the measurement channel is resealed.

[0023] Beneficial effects: By adopting the site dose rate measurement method, all actions are concentrated on the device's own shielding compensation structure and measurement channel, allowing operators to measure in a safe area and avoiding the uncertainties and additional risks caused by personnel moving around in complex environments, searching for interfaces, and temporarily handling equipment.

[0024] In one alternative implementation, a design process is also included before operation, which includes the following steps: designing a sleeve with a blind end based on the structural exterior wall conditions, the usage needs of the staff, and the requirements of standard specifications.

[0025] Beneficial effects: By adding a design process, the length, diameter and material of the sleeve are accurately calculated to ensure that the sleeve, as a through-hole component, can not only meet the mechanical and shielding requirements, but also achieve optimal structural integration and sealing with the existing wall.

[0026] In one alternative implementation, an installation process is included after the design process is completed and before the operation process begins. The installation process includes the following steps: pre-drilling mounting holes in the exterior wall of the structure; inserting a sleeve through the mounting holes, such that the blind end of the sleeve extends into the interior of the high-dose area and is sealed to the steel cladding of the high-dose area; filling the gap between the sleeve and the mounting holes with casting material; and installing a shielding compensation structure at the open end of the sleeve located on the maintenance site side.

[0027] Beneficial effects: By reserving installation holes, installing the sleeve inside the installation holes and extending it into the high-dose area, and sealing the blind end of the sleeve with the steel cladding of the high-dose area, static sealing is achieved, reducing the risk of leakage. Then, by filling the gap between the sleeve and the installation hole with casting material, a rigid wrapping and anchoring of the sleeve can be formed in the full circumference without gaps. Together, they serve as the core load-bearing structure to offset the load and achieve active repair and enhancement of the local shielding of the wall weakened by the opening. Attached Figure Description

[0028] To more clearly illustrate the technical solutions in the specific embodiments of the present invention, the drawings used in the description of the specific embodiments will be briefly introduced below. Obviously, the drawings described below are some embodiments of the present invention. For those skilled in the art, other drawings can be obtained from these drawings without creative effort.

[0029] Figure 1 This is a front view schematic diagram of the location dose rate measuring device with the measurement channel closed, provided in an embodiment of the present invention.

[0030] Figure 2 A front view schematic diagram of the location dose rate measuring device provided in an embodiment of the present invention when the measuring channel is opened and the probe is extended to the blind end of the sleeve; Figure 3 This is a front view schematic diagram of a location dose rate measuring device provided in an embodiment of the present invention; Figure 4 This is a side view schematic diagram of a location dose rate measuring device provided in an embodiment of the present invention; Figure 5 for Figure 4 Schematic diagram of the structure of the DD section; Figure 6 for Figure 4 Schematic diagram of the EE cross section; Figure 7 for Figure 4 Schematic diagram of the structure of the FF section; Figure 8 A schematic diagram of the clamping structure of the site dose rate measuring device provided in this embodiment of the invention when it is installed on the outer shielding block; Figure 9 A top view schematic diagram of the location dose rate measuring device provided in an embodiment of the present invention; Figure 10 This is a schematic flowchart of a site dose rate measurement method provided in an embodiment of the present invention.

[0031] Explanation of reference numerals in the attached figures: 101. Probe; 102. Alarm unit; 103. Connecting rod; 2. Sleeve; 201. Blind end; 202. Open end; 3. Shielding compensation structure; 301. Inner shielding block; 4. Sealing components; 5. Anchors; 6. Bolts; 7. Pin; 8. Handle; 9. Compression structure; A. High-dose areas; B. Exterior structural walls; C. Maintenance areas. Detailed Implementation

[0032] To make the objectives, technical solutions, and advantages of the embodiments of the present invention clearer, the technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of the present invention, not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.

[0033] During the operation of nuclear facilities, the external walls of high-radiation-dose areas (such as process equipment rooms or waste storage tanks) serve as the second line of defense for radiation safety. These areas typically house radioactive process piping, equipment, and storage tanks. Due to corrosion, wear, and aging caused by intense radiation during long-term operation, the equipment and fittings within these areas require regular maintenance or replacement. However, the radiation levels inside these areas are usually extremely high, and personnel cannot enter arbitrarily. Maintenance work can only be carried out after a prior assessment and confirmation that the radiation exposure received upon entry is controlled within safe levels.

[0034] Currently, the common radiation assessment method before entering high-dose areas is as follows: First, the area is initially cleaned and decontaminated. Then, personnel use a portable long-pole gamma dose rate meter and a portable aerosol sampler, inserted through pre-installed washout holes, to measure the gamma dose rate and aerosol radioactivity concentration. Based on the measurement results, a safety assessment is conducted, and personnel entry is only approved after confirming that the radiation protection requirements for personnel entry are met.

[0035] However, based on the principles of radiation protection—the legitimacy of radiation practices, optimization of radiation protection, and personal dose equivalent limits—when using a portable long-rod gamma meter to measure the site dose rate in a high-dose area through a washout hole, even though the high-dose area is continuously ventilated to maintain a negative pressure environment, deterministic and stochastic effects may still occur, causing contamination diffusion and cross-contamination, and posing internal and external radiation risks to the workers performing the measurement work. Therefore, it is difficult to fully meet the requirements of radiation protection.

[0036] To address this, the present invention provides a site dose rate measurement device and method. A sleeve 2 penetrates the outer wall B of the structure, with one end extending into the interior of the high-dose site A and designated as a blind end 201 (closed end). This effectively avoids internal radiation exposure and reduces the risk of external radiation dose during site dose rate measurement. It ensures that the monitoring points are not interconnected with the atmosphere of the high-dose site A and the maintenance area C during measurement operations, and maintains the shielding integrity and airtightness of the outer wall B of the high-dose site A during normal operation of the nuclear facility.

[0037] The following is combined with Figures 1 to 10 The following describes embodiments of the present invention.

[0038] According to an embodiment of the present invention, in one aspect, a site dose rate measuring device is provided, installed on the structural exterior wall B of a high-dose site A of a nuclear facility, and includes a monitor and a measurement interface assembly.

[0039] Specifically, such as Figure 1 and Figure 2 As shown, the monitoring instrument is equipped with a probe 101; the measurement interface assembly is embedded in the outer wall B of the structure. The measurement interface assembly includes a sleeve 2 and a shielding compensation structure 3. The sleeve 2 is installed through the outer wall B of the structure. One end of the sleeve 2 that extends into the high-dose area A has a closed blind end 201, and the end near the maintenance site C is an open end 202. A measurement channel is provided between the open end 202 and the blind end 201 along the axial direction of the sleeve 2. The shielding compensation structure 3 is installed on the outer wall B of the structure and covers the open end 202 of the sleeve 2. The shielding compensation structure 3 is used to open or close the measurement channel. When the measurement channel is closed, the shielding compensation structure 3 is used to compensate for the shielding effect lost due to the sleeve 2 penetrating the outer wall B of the structure, and to maintain the radiation shielding integrity of the outer wall B of the structure.

[0040] When the measurement channel is open, the probe 101 of the monitor can be inserted into the sleeve 2 through this channel and moved to the blind end 201 to measure the dose rate of the high-dose location A.

[0041] This setup, through the sleeve 2 pre-embedded in the outer wall B of the structure and its closed blind end 201, constructs a physical barrier to isolate the high-dose area A from the external maintenance area C. During measurement, only the probe 101 of the monitoring instrument needs to be inserted from the outside through the measurement channel opened by the shielding compensation structure 3. There is no need for personnel to bring the equipment into or near the high-dose area A, nor is there a need to temporarily puncture during measurement. This eliminates the risk of aerosol disturbance, equipment surface contamination diffusion (cross-contamination), and direct external and internal radiation exposure to the workers that may occur due to personnel entering the area.

[0042] Meanwhile, since the blind end 201 extends into the high-dose location A, its detector has completely penetrated the structural wall and directly detected the radiation field of the location under test, measuring the true location dose rate without additional attenuation by the wall, making the data more accurate.

[0043] It can be noted that the monitoring device is a portable long-pole gamma monitor, such as... Figure 2 As shown, it includes a probe 101, an alarm indication unit 102, and a connecting rod 103.

[0044] Specifically, the probe 101 is communicatively connected to the alarm prompting unit 102, which transmits the dose rate data at the entrance of the high-dose area A to the alarm prompting unit 102 for staff to view in real time and use the data to help determine whether the dose rate limit for personnel entry is met in the high-dose area A.

[0045] Furthermore, the connecting rod 103 is installed between the probe 101 and the alarm indication unit 102, and when in use, it is at least partially located inside the sleeve 2.

[0046] Furthermore, the connecting rod 103 adopts an electric telescopic rod structure, and the length of the connecting rod 103 can be adjusted as needed until the probe 101 moves to the blind end 201.

[0047] This setup allows the probe 101 to pass completely through the outer wall B of the structure, with the blind end 201 located in the radiation field inside the high-dose area A, thereby measuring the true location dose rate without additional attenuation from the wall, making the data more accurate.

[0048] It should be noted that, since the probe 101 of the portable long-pole gamma monitor is between 140 and 160 mm in length, such as Figure 2 As shown, in the horizontal direction, the distance between the blind end 201 of sleeve 2 and the inner wall of its adjacent structural outer wall B is at least 200mm.

[0049] Similarly, since the outer diameter of the portable long-rod gamma monitor probe 101 is in the range of 10~20mm, to ensure ease of operation for staff, such as Figure 1 , Figure 2 , Figure 3 and Figure 9 As shown, the vertical dimension (height) of sleeve 2 is at least 100mm to facilitate the insertion and removal of the monitoring instrument by the staff.

[0050] It can be explained that since the probe 101 is located inside the sleeve 2 and the staff is in the maintenance site C, the environment in the high-dose site A will not cause internal irradiation to the staff, nor will it cause cross-contamination to the maintenance site C.

[0051] After staff enter high-dose area A, based on the formula that the dose rate is inversely proportional to the square of the distance to the radiation source, the portable long-pole gamma monitor can be extended to a length of about 3m to determine the hot spot location, which can reduce the risk of external radiation to the human body.

[0052] In one embodiment, such as Figure 1 and Figure 3 As shown, the shielding compensation structure 3 includes a detachably connected inner shielding block 301 and an outer shielding block. The inner shielding block 301 is installed on the outer wall B of the structure, and the outer shielding block is installed on the side of the inner shielding block 301 near the maintenance site C.

[0053] With this configuration, the shielding compensation structure 3 includes a fixedly installed inner shielding block 301 and a detachable outer shielding block. The inner shielding block 301 serves as a basic shielding and sealing layer integrated with the outer wall of the structure B, providing the first and stable shielding guarantee in long-term non-measurement conditions. The outer shielding block, as an operable movable structure, is used to open or close the measurement channel as needed. This simplifies the operation of opening the measurement channel to a standard mechanical disassembly and assembly operation, requiring no special tools or complex procedures, and significantly improving operational efficiency.

[0054] When measurement is required, only the outer shielding block needs to be removed, while the inner shielding block 301 remains in place, minimizing the opening time and the exposed area of ​​the opening; when closed, the two shielding blocks are installed in sequence to achieve accurate and reliable compensation for the shielding capability at the penetration point.

[0055] In one embodiment, the shielding compensation structure 3 further includes a fastening mechanism for pressing and fixing the outer shielding block onto the inner shielding block 301.

[0056] With this setup, a dedicated fastening mechanism applies pressure to the outer shielding block, which can actively eliminate the microscopic gap at the interface between the outer shielding block and the inner shielding block 301. This ensures that the two shielding blocks function as a whole, effectively compensating for the weakening of interface shielding that may be introduced by the split structure, and eliminating the risk of radiation short circuit leakage from a mechanical perspective.

[0057] It should be noted that there are no specific limitations on the method of disassembling and connecting the inner shielding block 301 and the outer shielding block.

[0058] Specifically, one end of the outer shielding block is hinged to one end of the inner shielding block 301.

[0059] This configuration, by hinged one end of the outer shielding block to the inner shielding block 301, restricts the movement trajectory of the outer shielding block, ensuring that it can only open or close along a predetermined trajectory. This avoids the risk of the shielding block slipping, tipping over, or being bumped during disassembly, handling, and placement, and eliminates major safety hazards such as personal injury, equipment damage, or pollution spread caused by accidental falling of components.

[0060] Furthermore, the hinge connection between the outer shielding block and the inner shielding block 301 is not specifically limited.

[0061] As one implementation method, such as Figure 4 and Figure 6 As shown, bolt 6 and pin 7 are used. Bolt 6 is used to install on the outer wall B of the structure in the high-dose location A. Pin 7 serves as the rotation center of the outer shielding block, enabling the outer shielding block to rotate relative to the inner shielding block 301.

[0062] In one embodiment, such as Figure 1 , Figures 3 to 5 and Figure 8 As shown, the fastening mechanism includes a handle 8 and a clamping structure 9. The clamping structure 9 and the handle 8 work together to open or close the outer shielding block.

[0063] With this configuration, by using the clamping structure 9 and the handle 8 in linkage, the force applied by rotating or turning the handle 8 is amplified and oriented into a strong clamping force perpendicular to the contact surface through the mechanical principle of the clamping structure 9, which can ensure that the entire contact interface between the inner shielding block 301 and the outer shielding block is tightly fitted.

[0064] It can be noted that the end of the outer shielding block that is positioned relative to the pin 7 is the movable end.

[0065] Specifically, the clamping structure 9 includes a clamping block and an anchor bolt. The clamping block is fixed to the outer shielding block of the shielding compensation structure 3 by the anchor bolt. The outer shielding block is provided with an internal threaded hole that matches the external threaded protrusion of the anchor bolt. The clamping block is provided with a through mounting hole. During installation, the anchor bolt is inserted through the mounting hole and then screwed into the internal threaded hole, and gradually tightened.

[0066] The clamping block has an installation chamber on the side closest to the outer shielding block, so as to... Figure 5 For example, the installation chamber includes a cylindrical chamber and a spiral gradient chamber, combined with... Figure 10 As shown, the clamping block has an installation port on the side opposite to the outer shielding block that communicates with the installation chamber. The handle has a pressing bottom. During installation, the pressing bottom enters the installation chamber through the installation port.

[0067] Furthermore, the handle is also equipped with a threaded connecting post that connects to the pressing bottom. The mounting port is equipped with an internal thread that matches the threaded connecting post. After the pressing bottom enters the mounting chamber, the external thread on the outer circumference of the threaded connecting post is threadedly connected to the internal thread of the mounting port. Then, the operator continues to rotate the handle, gradually tightening the threaded connecting post, converting the rotational action into a linear movement of the pressing bottom relative to the outer surface of the outer shielding block. When the pressing bottom abuts against the outer surface of the outer shielding block, the threaded connecting post is tightened further. The pressing bottom will drive the outer shielding block to rotate around the movable end around the pin 7 toward the inner shielding block 301 until the outer shielding block and the inner shielding block 301 are securely connected.

[0068] Furthermore, the steps to disconnect the outer shielding block from the inner shielding block 301 are the reverse of the aforementioned process. For example, first loosen the threaded connecting post, and when the threaded connecting post is disengaged from the outer surface of the outer shielding block, the operator drives the handle in the direction away from the inner shielding block until the outer shielding block is disengaged from the inner shielding block 301.

[0069] It can be explained that, for example Figure 5 and Figure 7 As shown, the fastening mechanism also includes a connecting plate. One end of the connecting plate is provided with a pin hole for installing the pin 7. Similarly, the inner shielding block 301 is also provided with a pin hole. The two pin holes are staggered in the height direction. During installation, the pins are sequentially inserted into the two pin holes to complete the hinged connection between the inner shielding block 301 and the outer shielding block.

[0070] Furthermore, the other end of the connecting plate is fixed to the outer shielding block by bolt 6.

[0071] In one embodiment, such as Figure 1 , Figure 3 and Figure 9 As shown, a sealing element 4 is provided between the inner shielding block 301 and the open end 202 of the sleeve 2.

[0072] This configuration, by setting a seal 4 between the open end 202 of the sleeve 2 and the inner shielding block 301, forms a static sealing interface, blocking the leakage path of gas and particles, and preventing gas or aerosol leakage from the gaps generated when the sleeve 2 is installed with the wall, which helps to maintain the negative pressure environment in the high-dose area A.

[0073] It should be noted that no specific limitations are imposed on seal 4.

[0074] Due to the fact that the mating surfaces of the sleeve 2 opening end 202 and the inner shielding block 301 are inevitably subject to microscopic unevenness, stress deformation or slight misalignment during processing, installation and long-term thermal hydraulic load.

[0075] In one embodiment, the seal 4 is an elastic seal 4, such as an O-ring, a metal C-ring, or a flexible graphite gasket.

[0076] When in use, under the clamping action of the fastening mechanism, it can fill and adapt to these micro-defects, forming a dense sealing band. This ensures that even if the condition of the mating surface is not ideal during molding, a reliable seal can still be achieved through the elastic sealing mechanism of the sealing element 4, thereby reducing the requirements for machining and installation accuracy and reducing costs. At the same time, it can also achieve shock absorption.

[0077] In one embodiment, such as Figure 3 and Figure 9 As shown, the inner shielding block 301 is fixed to the outer wall B of the structure by the anchor 5.

[0078] With this configuration, the inner shielding block 301, as the core component that bears external operating forces (such as the clamping force of the fastening mechanism and the hinge force of the opening and closing of the outer shielding block) and maintains its own shielding integrity, is rigidly connected to the robust structural outer wall B through anchors 5 (such as high-strength chemical anchors and prestressed through bolts), forming a stable force transmission path. This allows the load to be effectively transmitted and distributed to the structural outer wall B through the anchors 5, preventing the inner shielding block 301 from loosening or shifting.

[0079] It can be noted that anchor 5 is an anchor bolt.

[0080] It can be noted that the blind end 201 is used for sealing connection with the steel cladding in the high-dose site A.

[0081] This configuration, by sealing the blind end 201 of sleeve 2 with the steel cladding of high-dose site A, forms an airtight isolation barrier, preventing radioactive gases or aerosols from leaking into the wall material or behind it through the construction gap between the outer wall of sleeve 2 and the pre-embedded hole in the outer wall of the structure B.

[0082] According to an embodiment of the present invention, in another aspect, a site dose rate measurement method is also provided, which employs the site dose rate measurement device provided in the first aspect.

[0083] like Figure 10 As shown, the location dose rate measurement method includes the following steps: When measurement is required, operate from the maintenance site C side, open the shielding compensation structure 3 of the measurement interface component to expose the measurement channel of the sleeve 2; insert the probe 101 of the monitor into the sleeve 2 through the measurement channel until its measurement end reaches or approaches the blind end 201 of the sleeve 2; measure the location dose rate in the high-dose location A through the monitor and obtain the measurement data; after the measurement is completed, remove the probe 101, close the shielding compensation structure 3, and re-close the measurement channel.

[0084] With this setup, by adopting the site dose rate measurement method, all actions are concentrated on the device's own shielding compensation structure 3 and measurement channel, allowing operators to measure in a safe area and avoiding the uncertainties and additional risks caused by personnel moving around in complex environments, searching for interfaces, and temporarily handling equipment.

[0085] In one embodiment, such as Figure 10 As shown, the design process is also included before the operation process. The design process includes the following steps: designing the sleeve 2 with blind end 201 according to the structural exterior wall B conditions, the usage needs of the staff and the requirements of standard specifications.

[0086] This design, through an added design process, precisely calculates the length, diameter, and material of sleeve 2, ensuring that sleeve 2, as a through-hole component, not only meets mechanical and shielding requirements but also achieves optimal structural integration and sealing with the existing wall.

[0087] It can be explained that the inner shielding block 301 needs to provide shielding compensation for the sleeve 2. The thickness, material and density of the shielding block are calculated from the size of the hollow area in the structural wall, the density and material of the structural wall. At the same time, necessary shielding compensation should be provided for the oblique rays at the joint of shielding materials with different shielding effects.

[0088] Preferably, the size of the inner shielding block 301 is larger than the size of the opening end 202 of the sleeve 2, and the size of the outer shielding block is greater than or equal to the size of the inner shielding block 301.

[0089] In one embodiment, such as Figure 10 As shown, the installation process is included after the design process is completed and before the operation process begins. The installation process includes the following steps: pre-drilling installation holes on the outer wall B of the structure; inserting the sleeve 2 through the installation hole so that the side of the sleeve 2 with the blind end 201 extends into the interior of the high-dose site A and is sealed to the steel cladding of the high-dose site A; filling the gap between the sleeve 2 and the installation hole with casting material; and installing the shielding compensation structure 3 at the open end 202 of the sleeve 2 located on the side of the maintenance site C.

[0090] This setup, by reserving mounting holes, installing sleeve 2 inside the mounting holes and extending it into the high-dose area A, and sealing the blind end 201 of sleeve 2 with the steel cladding of the high-dose area A, achieves static sealing, ensures the integrity of the shielding structure, and reduces the risk of leakage. Then, by filling the gap between sleeve 2 and the mounting hole with casting material, a rigid, circumferential, and gapless wrapping and anchoring of sleeve 2 can be formed, which together serve as the load-bearing core to offset the load and achieve active repair and enhancement of the local shielding of the wall weakened by the opening.

[0091] It should be noted that the mounting hole is preferably a square hole.

[0092] Although embodiments of the invention have been described in conjunction with the accompanying drawings, those skilled in the art can make various modifications and variations without departing from the spirit and scope of the invention, and such modifications and variations all fall within the scope defined by the appended claims.

Claims

1. A site dose rate measuring device, installed on the structural exterior wall (B) of a high-dose site (A) of a nuclear facility, characterized in that, include: The monitoring instrument is equipped with a probe (101). A measurement interface component, pre-embedded in the exterior wall (B) of the structure, the measurement interface component comprising: A sleeve (2) is provided through the outer wall (B) of the structure. One end of the sleeve (2) that extends into the high-dose area (A) is provided with a closed blind end (201), and the end near the maintenance site (C) is an open end (202). A measurement channel is provided between the open end (202) and the blind end (201) along the axial direction of the sleeve (2). A shielding compensation structure (3) is provided on the outer wall of the structure (B) and covers the opening end (202) of the sleeve (2). The shielding compensation structure (3) is used to open or close the measurement channel. When the measurement channel is closed, the shielding compensation structure (3) is used to compensate for the shielding effect lost due to the sleeve (2) penetrating the outer wall of the structure (B) and maintain the radiation shielding integrity of the outer wall of the structure (B). When the measurement channel is open, the probe (101) of the monitor can be inserted into the sleeve (2) through this channel and moved to the blind end (201) to measure the dose rate of the high dose location (A).

2. The location dose rate measuring device according to claim 1, characterized in that, The shielding compensation structure (3) includes a detachably connected inner shielding block (301) and an outer shielding block. The inner shielding block (301) is installed on the outer wall (B) of the structure, and the outer shielding block is installed on the side of the inner shielding block (301) near the maintenance site (C).

3. The location dose rate measuring device according to claim 2, characterized in that, The shielding compensation structure (3) also includes a fastening mechanism for pressing and fixing the outer shielding block onto the inner shielding block (301).

4. The location dose rate measuring device according to claim 3, characterized in that, The fastening mechanism includes a handle (8) and a clamping structure (9), which, in conjunction with the handle (8), opens or closes the outer shielding block.

5. The location dose rate measuring device according to any one of claims 2-4, characterized in that, One end of the outer shielding block is hinged to one end of the inner shielding block (301).

6. The location dose rate measuring device according to any one of claims 2-4, characterized in that, A sealing element (4) is provided between the inner shielding block (301) and the open end (202) of the sleeve (2).

7. The location dose rate measuring device according to any one of claims 2-4, characterized in that, The inner shielding block (301) is fixed to the outer wall of the structure (B) by anchors (5).

8. The in-situ dose rate measuring device according to any one of claims 1 to 4, characterized in that, The blind end (201) is used for a sealed connection with the steel cladding in the high-dose site (A).

9. A method for measuring site dose rate, characterized in that, The location dose rate measuring device according to any one of claims 1-8 includes an operating process, which includes the following steps: When measurement is required, operate from the maintenance site (C) side, open the shielding compensation structure (3) of the measurement interface component, and expose the measurement channel of the sleeve (2); Insert the probe (101) of the monitor into the sleeve (2) through the measurement channel until its measuring end reaches or approaches the blind end (201) of the sleeve (2). The location dose rate in the high-dose location (A) is measured using a monitoring instrument, and the measurement data is obtained. After the measurement is completed, remove the probe (101), close the shielding compensation structure (3), and reseal the measurement channel.

10. The location dose rate measurement method according to claim 9, characterized in that, Prior to the execution process, there is also a design process, which includes the following steps: Based on the structural exterior wall (B) conditions, the usage needs of the staff, and the requirements of the standard specifications, a sleeve (2) with a blind end (201) is designed.

11. The site dose rate measurement method according to claim 10, characterized in that, The process, which is completed after the design process but before the operation begins, also includes an installation process, which includes the following steps: Pre-drill mounting holes on the exterior wall (B) of the structure; The sleeve (2) is inserted through the mounting hole, so that the side of the sleeve (2) with the blind end (201) extends into the interior of the high dose site (A) and is sealed to the steel cladding of the high dose site (A); Fill the gap between the sleeve (2) and the mounting hole with casting material; A shielding compensation structure (3) is installed at the open end (202) of the sleeve (2) located on the side of the maintenance site (C).

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