CN111123346A - Nuclear power station burn-in test platform - Google Patents

Nuclear power station burn-in test platform Download PDF

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Publication number
CN111123346A
CN111123346A CN201911243238.6A CN201911243238A CN111123346A CN 111123346 A CN111123346 A CN 111123346A CN 201911243238 A CN201911243238 A CN 201911243238A CN 111123346 A CN111123346 A CN 111123346A
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CN
China
Prior art keywords
nuclear power
drawer
test platform
power station
plate
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CN201911243238.6A
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Chinese (zh)
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CN111123346B (en
Inventor
李广锋
李明钢
杨志斌
沙洪伟
邵帅
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China General Nuclear Power Corp
CGN Power Co Ltd
Daya Bay Nuclear Power Operations and Management Co Ltd
Lingdong Nuclear Power Co Ltd
Guangdong Nuclear Power Joint Venture Co Ltd
Lingao Nuclear Power Co Ltd
Original Assignee
China General Nuclear Power Corp
CGN Power Co Ltd
Daya Bay Nuclear Power Operations and Management Co Ltd
Lingdong Nuclear Power Co Ltd
Guangdong Nuclear Power Joint Venture Co Ltd
Lingao Nuclear Power Co Ltd
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Application filed by China General Nuclear Power Corp, CGN Power Co Ltd, Daya Bay Nuclear Power Operations and Management Co Ltd, Lingdong Nuclear Power Co Ltd, Guangdong Nuclear Power Joint Venture Co Ltd, Lingao Nuclear Power Co Ltd filed Critical China General Nuclear Power Corp
Priority to CN201911243238.6A priority Critical patent/CN111123346B/en
Publication of CN111123346A publication Critical patent/CN111123346A/en
Application granted granted Critical
Publication of CN111123346B publication Critical patent/CN111123346B/en
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    • GPHYSICS
    • G01MEASURING; TESTING
    • G01TMEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T7/00Details of radiation-measuring instruments
    • G01T7/005Details of radiation-measuring instruments calibration techniques

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  • Physics & Mathematics (AREA)
  • Health & Medical Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Physics & Mathematics (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Molecular Biology (AREA)
  • Spectroscopy & Molecular Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention belongs to the technical field of nuclear power station radiation protection, and particularly relates to a nuclear power station burn-in test platform. This nuclear power station test platform of beating includes: the device comprises an on-site processing unit, a radioactive probe, a remote display unit, a main body frame and a side wall outer plate; the side wall outer plate is enclosed into an accommodating space with a side opening, and the main body frame is arranged in the accommodating space; the in-situ processing unit is connected to one side of the main body frame opposite to the side opening; the main body frame is provided with a first drawer for installing the remote display unit, a second drawer for installing the radioactive probe and a third drawer for installing radioactive source substances; a lifting platform for adjusting the distance between the radioactive source substance and the radioactive probe is arranged in the third drawer. The nuclear power station burn-in test platform sequentially installs the detection equipment required by the nuclear power station burn-in, reduces the risk of damage to the radiation monitoring equipment, and enables the nuclear power station radiation monitoring equipment to be effectively tracked and maintained.

Description

Nuclear power station burn-in test platform
Technical Field
The invention belongs to the technical field of nuclear power station radiation protection, and particularly relates to a nuclear power station burn-in test platform.
Background
The nuclear power plant is a power plant which generates electric energy by using energy released by a nuclear fission reaction, equipment of the nuclear power plant needs to ensure the safety and the stability of the equipment, and once the equipment fails, a long time and huge manpower are consumed for maintenance and treatment, so that huge economic loss can be brought to the nuclear power plant; therefore, equipment in the nuclear power station needs to be copied off line in a specific environment before installation so as to ensure the stability and safety after field installation.
When nuclear power station equipment is used for offline copy, the working environment of the nuclear power equipment needs to be simulated, and components such as a radioactive probe, an on-site processing unit, an equipment cable and a remote display unit which comprise a measurement circuit need to be used during copy. At present, off-line copying of nuclear power plant radiation monitoring equipment is carried out on a desktop or the ground, randomness of the nuclear power plant radiation monitoring equipment used during copying is high, the nuclear power plant radiation monitoring equipment scatters and is out of order during copying, copying efficiency is low, and running state of the nuclear power plant radiation monitoring equipment is tracked.
Disclosure of Invention
The invention solves the problems of low copying efficiency, difficulty in tracking equipment state and the like caused by disordered scattering of equipment when the nuclear power station radiation monitoring equipment is copied offline in the prior art, and provides a nuclear power station copying test platform.
In view of the above problems, an embodiment of the present invention provides a method for laser processing a through hole in a glass substrate, including: the device comprises an on-site processing unit, a radioactive probe, a remote display unit, a main body frame and a side wall outer plate; the side wall outer plate is enclosed into an accommodating space with an opening on the side surface, and the main body frame is arranged in the accommodating space;
the in-situ processing unit is connected to one side of the main body frame opposite to the side opening;
the main body frame is provided with a first drawer for installing the remote display unit, a second drawer for installing the radioactive probe and a third drawer for installing radioactive source substances; the first drawer, the second drawer and the third drawer are arranged in parallel; and a lifting platform for adjusting the distance between the radioactive source substance and the radioactive probe is arranged in the third drawer.
Optionally, the first drawer is of a non-drawable structure, a first transparent door is arranged at a position, corresponding to the first drawer, on the side wall outer plate, and a second transparent door is arranged at a position, corresponding to the second drawer, on the side wall outer plate; the second drawer and the third drawer are both of drawable structures.
Optionally, a fourth drawer for storing tools is further arranged on the main body frame; the fourth drawer is of a drawable structure and is arranged in parallel with the first drawer.
Optionally, a first groove is further formed in the main body frame, and the nuclear power station burn-out test platform further comprises an automatic rope winder installed in the groove.
Optionally, the nuclear power station burn-in test platform further comprises a first bottom plate connected to the bottom of the side wall outer plate, and a first roller is arranged on the first bottom plate; a reinforcing upright post vertical to the first bottom plate is arranged at the inner edge of the main body frame; and a first handle is arranged on the side wall outer plate.
Optionally, the main body frame includes casing, diaphragm and riser, the diaphragm with the riser is all installed on the casing, the diaphragm with the riser is connected and contained angle between the two is greater than 90 degrees.
Optionally, the vertical plate is provided with a slot and a baffle plate for limiting the installation position of the in-situ processing unit; the on-site processing unit is provided with an inserting plate and connected to the vertical plate through the inserting plate inserted into the inserting groove.
Optionally, the vertical plate is provided with a wire guide hole, the main body frame further includes a wire guide tube arranged in the first drawer, one end of the wire guide tube is communicated with the wire guide hole, and the other end of the wire guide tube is communicated with the second drawer.
Optionally, the nuclear power station burn-in test platform further comprises a lead chamber trolley detachably connected to the side wall outer plate;
the lead chamber trolley comprises a trolley body and a box body used for mounting the radioactive probe, and a second groove used for bearing the box body is formed in the trolley body; and the vehicle body is also provided with a second roller and a second handle.
Optionally, the box body comprises a first cover plate, a lead chamber body, a probe clamp and a telescopic rod; the telescopic rod is connected between the first cover plate and the lead chamber body, and the probe clamp is installed in the lead chamber body.
Optionally, the lead chamber body comprises a first lead chamber body, a second lead chamber body and a movable partition plate, wherein the movable partition plate is arranged between the first lead chamber body and the second lead chamber body.
Optionally, the probe fixture includes a fixture housing, a fixture body, and an adjustment assembly; the clamp body is arranged in the clamp shell and is provided with a containing part for fixing the radioactive probe; the fixture comprises a fixture shell, and is characterized in that a first adjusting hole is formed in the fixture shell, a second adjusting hole is formed in the fixture body, and the adjusting assembly penetrates through the first adjusting hole and the second adjusting hole and then extends into the accommodating part.
Optionally, the clamp body comprises a first clamp block, a second clamp block and a shell of which the outer wall is connected with the clamp shell; the accommodating part is formed by the first clamp block and the second clamp block;
the adjusting component comprises a first adjusting screw rod which penetrates through the first adjusting hole and is connected with the first clamp block through the second adjusting hole, and a second adjusting screw rod which penetrates through the first adjusting hole and is connected with the second clamp block through the second adjusting hole.
Optionally, a first sliding hole is formed in the first clamp block, and a second sliding hole is formed in the second clamp block at a position opposite to the first sliding hole; the adjusting component also comprises a sliding rod with two ends respectively inserted in the first sliding hole and the second sliding hole, and a spring sleeved on the sliding rod; the slide bar is connected with the first clamp block and the second clamp block in a sliding mode, and two ends of the spring are respectively abutted to the first clamp block and the second clamp block.
Optionally, the shell comprises a front liner plate, a rear liner plate, a left liner plate, a right liner plate, a second bottom plate and a second cover plate with a round hole; a cushion pad is arranged on the second bottom plate; one end of the radioactive probe penetrates through the round hole to be installed in the accommodating part, and the bottom of the radioactive probe is positioned on the buffer pad; the first adjusting screw rod drives the first clamp block to be attached to the radioactive probe, and the second adjusting screw rod drives the second clamp block to be attached to the radioactive probe.
The nuclear power station burn-in test platform provided by the embodiment can be used for orderly installing nuclear power station radiation monitoring equipment, including a radioactive probe, a local processing unit, a remote display unit, a cable and the like, and the nuclear power station radiation monitoring equipment to be burned in a nuclear power station is connected through an external connector on the nuclear power station radiation monitoring equipment to be burned in the nuclear power station to be burned, so that the problem that the radiation monitoring equipment is scattered and disordered when a nuclear power station tester is burned in the nuclear power station is solved, the risk that the radiation monitoring equipment is damaged is reduced, meanwhile, the nuclear power station radiation monitoring equipment can be effectively tracked and maintained, in addition, the nuclear power station burn-in test platform has a shielding effect on the radioactive probe, and the radiation dose of the radioactive probe on the nuclear power; on the other hand, nuclear power station testers can move the nuclear power station burn-in test platform to a preset burn-in place according to different test sites to perform burn-in operation, so that the maneuverability of the nuclear power station burn-in test platform is improved, and the burn-in efficiency of the nuclear power station testers is improved; finally, the nuclear power station burn-in test platform accessible the third drawer in the altitude mixture control of elevating platform realizes the radioactive probe with the regulation of distance between the radioactive substance reaches with this the radioactive probe can mark the function of radioactive substance, promptly the nuclear power station burn-in test platform provides the platform on a simulation nuclear power station scene, and nuclear power station tester need not to get into the radioactive region of nuclear power station and can realize the nuclear power station and wait the work of burning-in of equipment, has improved nuclear power station tester's work efficiency and has guaranteed nuclear power station tester's health effectively.
Drawings
The invention is further illustrated with reference to the following figures and examples.
Fig. 1 is a schematic perspective view of a nuclear power station burn-in test platform according to an embodiment of the present invention;
fig. 2 is a schematic perspective view of a main frame of a nuclear power plant burn-in test platform according to an embodiment of the present invention;
fig. 3 is a schematic perspective view of a side wall outer plate of a nuclear power station burn-in test platform according to an embodiment of the present invention;
fig. 4 is a schematic perspective structural view of a housing of a main body frame of a nuclear power plant burn-in test platform according to an embodiment of the present invention;
FIG. 5 is a schematic perspective view of a housing of a main frame of a nuclear power plant burn-in test platform according to another embodiment of the present invention;
FIG. 6 is a wiring diagram of the radioactive probe, the local processing unit, the remote display unit and the power supply of the nuclear power station burn-in test platform according to an embodiment of the present invention;
fig. 7 is a schematic perspective view of a nuclear power plant burn-in test platform according to another embodiment of the present invention;
FIG. 8 is a schematic structural diagram of a lead chamber trolley of a nuclear power station burn-in test platform according to an embodiment of the invention;
fig. 9 is a schematic structural diagram of a radioactive probe of a nuclear power plant burn-in test platform according to an embodiment of the present invention, which is mounted on a probe clamp;
FIG. 10 is a cross-sectional view of a clamp body of a nuclear power station burn-in test platform according to an embodiment of the invention;
the reference numerals in the specification are as follows:
1. an in-situ processing unit; 2. a radioactive probe; 3. a remote display unit; 4. a main body frame; 41. a first drawer; 411. a first transparent door; 42. a second drawer; 421. a second transparent door; 43. a third drawer; 44. a fourth drawer; 45. an automatic rope winder; 451. a first groove; 46. a housing; 461. reinforcing the upright post; 47. a transverse plate; 48. a vertical plate; 481. a slot; 482. a baffle plate; 483. a wire guide hole; 49. a conduit; 5. a side outer plate; 51. a first base plate; 52. a first roller; 53. a first handle; 6. a lead chamber trolley; 61. a vehicle body; 611. a second groove; 612. a second roller; 613. a second handle; 62. a box body; 621. a first cover plate; 622. a lead chamber body; 6221. a first lead chamber body; 6222. a second lead chamber body; 6223. a movable partition plate; 623. a probe clamp; 6231. a clamp housing; 6232. a clamp body; 62321. a receptacle portion; 62322. a first clamp block, 62323, a second clamp block; 62324. a housing; 623241, a cushion pad; 623242, a second cover plate; 6233. an adjustment assembly; 62331. a first adjusting screw; 62332. a slide bar; 62333. a spring; 624. a telescopic rod.
Detailed Description
In order to make the technical problems, technical solutions and advantageous effects solved by the present invention more clearly apparent, the present invention is further described in detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the invention and are not intended to limit the invention.
It is to be understood that the terms "upper", "lower", "left", "right", "front", "rear", "middle", and the like, indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings, are only for convenience in describing the present invention and simplifying the description, and do not indicate or imply that the device or element referred to must have a particular orientation, be constructed in a particular orientation, and be operated, and thus, should not be construed as limiting the present invention.
As shown in fig. 1, fig. 2, fig. 3, and fig. 5, a nuclear power station burn-in test platform according to an embodiment of the present invention includes: the radiation monitoring device comprises a radioactive probe 2 (radiation dosage equipment for measuring environment), an on-site processing unit 1 (equipment for processing signals collected and output by the radioactive probe 2 and completing analog-to-digital conversion and operation of the signals), a remote display unit 3 (equipment for converting the signals processed by the on-site processing unit 1 into signals of a standard metering unit and displaying the signals), a main body frame 4 and a side wall outer plate 5; the side wall outer plate 5 encloses an accommodating space with an opening on the side surface, and the main body frame 4 is arranged in the accommodating space; it can be understood that the main body frame 4 is detachably connected with the side wall outer panel 5, and the side wall outer panel 5 protects the main body frame 4.
The in-situ processing unit 1 is connected to the main body frame 4 at a side opposite to the side opening; the main body frame 4 is detachably connected with one or more on-site processing units 1, and the corresponding nuclear power station copying test platform can simultaneously meet the requirement of simultaneous copying work of multiple sets of devices to be copied, so that the copying work efficiency of nuclear power station testers is improved; it can be understood that, the remote display unit 3 corresponds to the on-site processing unit 1, and a plurality of the remote display units 3 can be correspondingly installed, that is, data of a plurality of sets of devices to be copied during copying can be displayed.
Meanwhile, a main power switch button and a corresponding shunt power switch button of the base processing unit are also arranged on the side wall outer plate 5, wherein the shunt power switch button is determined according to the number of the on-site processing units 1; a nuclear power station tester can selectively turn on (and/or turn off) the main power switch button and the shunt power switch button on the side wall outer plate 5 according to the requirements during on-site machine copying.
A first drawer 41 for installing the remote display unit 3, a second drawer 42 for installing the radioactive probe 2 and a third drawer 43 for installing radioactive source materials (such as radioactive sources like Cs-137) are arranged on the main body frame 4; the first drawer 41, the second drawer 42 and the third drawer 43 are arranged in parallel; a lifting table (not shown) for adjusting the distance between the radioactive source material and the radioactive probe 2 is provided in the third drawer 43. It is understood that the lifting platform in the third drawer 43 can adjust the distance between the radioactive material and the radioactive probe 2, so that the elements radiated by the radioactive material can be detected by the radioactive probe 2; specifically, the lifting platform is arranged in the middle of the third drawer 43, and the height of the lifting platform is adjusted and fixed after adjustment through screws which penetrate through the third drawer 43 and are matched with stepped grooves in the lifting platform; preferably, the adjustable range of the distance between the radioactive probe 2 mounted on the lifting table and the radioactive substance is 80mm to 200mm, for example, the distance between the radioactive probe 2 and the radioactive substance is: 80mm, 150mm, 200mm, etc.
The nuclear power station burn-in test platform provided by the embodiment can be used for orderly installing nuclear power station radiation monitoring equipment, and comprises a radioactive probe 2, a local processing unit 1, a remote display unit 3, a cable and other nuclear power station radiation monitoring equipment, and the nuclear power station radiation monitoring equipment to be burned is connected through an external connector on the nuclear power station radiation monitoring equipment, so that the problem that the radiation monitoring equipment scatters and falls out of order when nuclear power station testers burn the nuclear power station is solved, the risk that the radiation monitoring equipment is damaged is reduced, the nuclear power station radiation monitoring equipment can be effectively tracked and maintained, meanwhile, the nuclear power station burn-in test platform plays a shielding effect on the radioactive probe 2, and the radiation dose of the radioactive probe 2 on the nuclear power station testers is reduced; on the other hand, nuclear power station testers can move the nuclear power station burn-out test platform to a preset burn-out place according to different test sites to perform burn-out operation, so that the maneuverability of the nuclear power station burn-out test platform is improved, and the work efficiency of the nuclear power station testers is improved; finally, nuclear power station diagnostic test platform accessible in the third drawer 43 the altitude mixture control of elevating platform realizes radioactive probe 2 with the regulation of distance between the radioactive substance, in order to reach radioactive probe 2 can mark the function of radioactive substance, promptly nuclear power station diagnostic test platform provides the platform on a simulated nuclear power station scene, and nuclear power station tester need not to get into the radioactive region of nuclear power station and can realize the diagnostic work of nuclear power station equipment of waiting to diagnose, has further improved nuclear power station tester's work efficiency and has guaranteed nuclear power station tester's health effectively.
In an embodiment, as shown in fig. 4 and 5, the first drawer 41 is of a non-drawable structure, a first transparent open door 411 is disposed at a position on the side wall outer panel 5 corresponding to the first drawer 41, and a second transparent open door 421 is disposed at a position on the side wall outer panel 5 corresponding to the second drawer 42; specifically, the first drawer 41 is fixed on the upright posts at four corners of the main body frame 4, and a plurality of remote display units 3 (corresponding to the base processing unit) can be placed in the first drawer 41 at the same time, so that the requirement of simultaneous copying of multiple sets of equipment can be met, and the first transparent door 411 structure designed by the first drawer 41 is advantageous for connecting related cables and installing the remote display units 3 into the first drawer 41 when the first transparent door 411 side is opened (compared with the drawing of the drawer, the opening range of the door is larger); further, the second drawer 42 is used for placing the radioactive probe 2, and is simultaneously provided with a drawer of a drawable type and a second transparent door 421 structure, so that nuclear power plant testers can conveniently take and place the radioactive probe 2 and the clamp of the radioactive probe 2 and wire and observe the radioactive probe 2 in the copying process (specifically, the radioactive probe 2 or the probe clamp 623 provided with the radioactive probe 2 is drawn into the second drawer 42 through the drawable type, and the wire connection of the radioactive probe 2 is completed by opening the second transparent door 421). Both the second drawer 42 and the third drawer 43 are of a drawable construction. It is understood that the first transparent door 411 and the second transparent door 421 are both made of transparent glass or transparent plastic or the like disposed on the outer side gusset panel 5.
In one embodiment, as shown in fig. 4 and 5, the main frame 4 is further provided with a fourth drawer 44 for storing tools; the fourth drawer 44 is of a drawable structure and is disposed parallel to the first drawer 41. It is understood that the fourth drawer 44 is disposed at the bottom of the main body frame 4, and in particular, the first drawer 41, the second drawer 42, the third drawer 43 and the fourth drawer 44 are sequentially disposed in parallel on a main plane of the main body frame 4 away from the on-site processing unit 1; the fourth drawer 44 is used for storing tools such as cables, multimeters and screwdrivers, when nuclear power plant testers need to perform test experiments or copy machines, corresponding tools can be directly found from the fourth drawer 44, steps of finding tools are reduced, and working efficiency of the nuclear power plant testers is further improved.
In an embodiment, as shown in fig. 4, the main body frame 4 is further provided with a first groove 451, and the nuclear power station serger test platform further comprises an automatic rope winder 45 installed in the first groove 451. Understandably, automatic ropewinder 45 is used for getting up very long cable conductor roll-up, can pull by oneself and connect outside equipment of waiting to copy when nuclear power station tester need copy the machine work, should automatic ropewinder 45 set up that the hookup location is more complicated (high radiation region, high-voltage region etc.) and the nuclear power station of distance ratio far away waits to copy the machine equipment, has promoted the convenience that this copy machine test platform used.
In an embodiment, as shown in fig. 1 and 4, the nuclear power station burn-in test platform further includes a first bottom plate 51 connected to the bottom of the side wall outer plate 5, and a first roller 52 (universal wheel, etc., which can be provided with a brake structure) is arranged on the first bottom plate 51; a reinforcing upright column 461 perpendicular to the first bottom plate 51 is arranged at the inner edge of the main body frame 4; and a first handle 53 is arranged on the side wall outer plate 5. It can be understood that the reinforcing columns 461 are fixedly connected at four inner corner positions of the main body frame 4, so as to enhance the strength of the main body frame 4, i.e. prolong the service life of the burn-in test platform of the nuclear power station. The first handle 53 is arranged at one end of the side wall outer plate 5, which is far away from the main body frame 4. Specifically, the first handle 53 is fixedly connected to the upper portion of the side wall outer plate 5, so that nuclear power station inspection personnel can conveniently move the nuclear power station burn-out test platform.
In one embodiment, as shown in fig. 2 and 4, the main body frame 4 includes a housing 46, a horizontal plate 47 and a vertical plate 48, the horizontal plate 47 and the vertical plate 48 are both mounted on the housing 46, the horizontal plate 47 is connected to the vertical plate 48, and an included angle between the horizontal plate 47 and the vertical plate 48 is greater than 90 degrees. It is to be understood that the first drawer 41, the second drawer 42, the third drawer 43, the fourth drawer 44, etc. mentioned above are all provided on the housing 46; the transverse plate 47 is installed at the top of the shell 46, and a platform for placing equipment such as computers and the like by nuclear power plant testers is further provided on the surface of the transverse plate 47, which is far away from the first bottom plate 51; specifically, the horizontal plate 47 and the vertical plate 48 may be integrally formed, an included angle between the horizontal plate 47 and the vertical plate 48 is greater than 90 degrees, for example, 95 degrees, 100 degrees, etc., an internal installation space of the main body frame 4 is enlarged (as shown in fig. 4, a first groove 451 for installing the automatic rope winder 45 is provided), and the vertical plate 48 and the horizontal plate 47 are detachably connected with the main body frame 4.
In one embodiment, as shown in FIG. 2, the riser 48 is provided with a slot 481 and a baffle 482 limiting the installation position of the in-situ processing unit 1; an insertion plate (not shown) is arranged on the in-situ processing unit 1, and the in-situ processing unit 1 is connected to the vertical plate 48 through the insertion plate inserted into the insertion groove 481. It can be understood that a plurality of slots 481 and baffles 482 can be arranged on the vertical plate 48, that is, the copying work of equipment to be copied in a plurality of nuclear power plants can be met simultaneously, and the copying work efficiency of nuclear power plant testers is improved.
Preferably, as shown in fig. 1, the vertical plate 48 is provided with a wire hole 483, the main body frame 4 further includes a wire conduit 49 disposed in the first drawer 41, one end of the wire conduit 49 is communicated with the wire hole 483, and the other end of the wire conduit 49 is communicated with the second drawer 42. Specifically, the connecting cable of the radioactive probe 2 is connected with the left interface at the upper end of the on-site processing unit 1 through the conduit 49, the left interface at the lower end of the on-site processing unit 1 is connected with a power supply (an external 220V direct current power supply), and the right interface at the lower end is electrically connected with the remote display unit 3 placed in the first drawer through a cable, so that a nuclear power station tester can copy the external equipment to be copied outside the nuclear power station.
Furthermore, a plurality of wire insertion holes and a cable clamp arranged close to the baffle 482 are formed in the vertical plate 48; as shown in fig. 1 and 6, the connecting wires at the lower end of the in-situ processing unit 1 can be fixed on the vertical plates 48 through the cable clips and extend into the shell 46 through the wire insertion holes to connect the related components; the on-site processing unit 1, the remote display unit 3 and the radioactive probe 2 are electrically connected through the embodiment and then matched with the radioactive substance to simulate the radioactive source of the nuclear power station, so that the copying work of the equipment to be copied of the nuclear power station tester is realized.
In summary, in this embodiment, cables can be orderly arranged among the in-situ processing unit 1, the remote display unit 3, and the radioactive probe 2 on the nuclear power plant burn-in test platform. The wiring work of nuclear power station testers is facilitated, and the management of the nuclear power station burn-in test platform is facilitated.
In an embodiment, as shown in fig. 7 and 8, the nuclear power station burn-in test platform further comprises a lead chamber trolley 6 detachably connected (hitched, bolted, etc.) to the side wall outer plate 5;
the lead chamber trolley 6 comprises a trolley body 61 and a box body 62 for mounting the radioactive probe 2, wherein a second groove 611 for bearing the box body 62 is formed in the trolley body 61; the vehicle body 61 is further provided with a second roller 612 and a second handle 613. It is understood that the box 62 is used for storing the radioactive probe 2, the vehicle body 61 is used for transporting the radioactive probe 2, and the nuclear power plant tester can push the second handle 613 to move the lead chamber trolley 6 independently, and can also connect the lead chamber trolley 6 to the outer side wall panel 5 to form a whole.
According to the nuclear power station burn-in test platform provided by the embodiment, when nuclear power station testers need to perform a radiation-proof experiment by using the radioactive probe 2, the lead chamber trolley 6 is connected to the side wall outer plate 5 and pushed to a preset experiment site; when an anti-radiation experiment is not needed, the radiation probe 2 is directly placed in the second drawer without connecting the lead chamber trolley 6 to the side wall outer plate 5. The design of the lead chamber trolley 6 facilitates the nuclear power station testing personnel to take the radioactive probe 2 when the nuclear power station testing personnel are used as a radiation laboratory, and the working efficiency of the nuclear power station testing personnel for radiation experiments is improved. In addition, the box body 62 is used for storing and carrying the radioactive probe 2, so that the radiation quantity of the radioactive probe 2 to nuclear power station testers is reduced, and the health of the nuclear power station testers is ensured.
In one embodiment, as shown in fig. 8, the case 62 includes a first cover 621, a lead chamber 622, a probe clamp 623, and a telescopic rod 624; the extension bar 624 is connected (screwed, etc.) between the first cover 621 and the lead chamber 622, and the probe clamp 623 is installed in the lead chamber 622. It will be appreciated that the extension bar 624 acts to support the first cover 621, and when the case 62 is closed, the extension bar 624 is compressed into the case 62, the probe holder 623 is used to store the radiation probe 2, and the lead chamber 622 is used to store the probe holder 623.
In an embodiment, as shown in fig. 8, the lead chamber body 622 comprises a first lead chamber body 6221, a second lead chamber body 6222 and a movable diaphragm 6223, the movable diaphragm 6223 being disposed between the first lead chamber body 6221 and the second lead chamber body 6222. Due to the different sizes of the probe clamps 623 (designed according to the sizes of the corresponding radioactive probes 2), and the sizes of the spaces of the first lead chamber 6221 or the second lead chamber 6222 required for installing the radioactive probes 2 are also different, the movable partition 6223 is disposed between the first lead chamber 6221 and the second lead chamber 6222 (clamped by the probe clamps 623 in the first lead chamber 6221 and the probe clamps 623 in the second lead chamber 6222 together) to change the sizes of the spaces of the first lead chamber 6221 and the second lead chamber 6222. The movable partition 6223 prevents the two radioactive probes 2 mounted in the box 62 from interfering with each other (the radioactive materials emitted from the radioactive probes 2 may interfere with the quality of the radioactive probes 2), so as to prolong the service life of the radioactive probes 2.
In one embodiment, as shown in fig. 9, the probe clamp 623 includes a clamp housing 6231, a clamp body 6232, and an adjustment assembly 6233; the holder body 6232 is provided inside the holder case 6231 and has a receiving portion (not shown) for fixing the radiation probe 2; a first adjusting hole (not shown) is formed in the clamp shell 6231, a second adjusting hole (not shown) is formed in the clamp body 6232, and the adjusting assembly 6233 penetrates through the first adjusting hole and the second adjusting hole and then extends into the accommodating portion. It is understood that a plurality of the first adjusting holes may be disposed on the clamp body 6231, a plurality of the second adjusting holes may be disposed on the clamp body 6232, and a plurality of the corresponding adjusting assemblies 6233 may be disposed for adjusting the size of the accommodating portion (so that the radioactive probe 2 is tightly mounted in the accommodating portion of the clamp body 6232); in addition, the adjusting assembly 6233 may be a screw, a telescopic rod 624, or other structural members connected inside the clamp body 6232.
In one embodiment, as shown in fig. 10 and 11, the clamp body 6232 includes a first clamp block 62322, a first clamp block 62323, and a housing 62324 having an outer wall connected to the clamp housing 6231; the first clamp block 62322 and the first clamp block 62323 define the receptacle therebetween; it will be appreciated that the first clamp block 62322 and the first clamp block 62323 enclose the receptacle for mounting the radiation probe 2; specifically, the first clamp block 62322 and the first clamp block 62323 have a semi-cylindrical (middle formed with a groove) structure for fixing one end of the radiation probe 2.
The adjustment assembly 6233 includes a first adjustment screw 62331 coupled to the first clamp block 62322 through the first and second adjustment holes (threaded holes, etc.), and a second adjustment screw (not shown) coupled to the first clamp block 62323 through the first and second adjustment holes. It is to be appreciated that the first and second threaded rods include adjustment nuts for turning the threaded rods to change the relative positions of the first clamp block 62322 and the first clamp block 62323 and a threaded rod connecting the first clamp block 62322 and the first clamp block 62323; the first clamp block 62322 and the first clamp block 62323 are not connected to the housing 62324 (i.e., the first clamp block 62322 and the first clamp block 62323 are movable within the housing 62324), the housing 62324 is connected to an inner wall of the clamp housing 62324; the radioactive probe 2 is tightly installed in the accommodating portion by the cooperation of the first adjusting screw 62331 and the second adjusting screw.
In one embodiment, as shown in fig. 10, a first sliding hole (not shown) is formed on the first clamp block 62322, and a second sliding hole (not shown) is formed on the first clamp block 62323 at a position opposite to the first sliding hole; the adjusting assembly 6233 further comprises a sliding rod 62332 with two ends respectively inserted into the first sliding hole and the second sliding hole, and a spring 62333 sleeved on the sliding rod 62332; it is understood that the slide bar 62332 is disposed inside the clamp block near the inner wall, and the slide bar 62332 may be provided in plurality; the slide bar 62332 is slidably connected to the first clamp block 62322 and the first clamp block 62323 (i.e. the first clamp block 62322 and the first clamp block 62323 can move relatively on the slide bar under the action of external force), and two ends of the spring 62333 abut against the inner walls of the first clamp block 62322 and the first clamp block 62323, respectively. Specifically, the spring 62333 is disposed on the slide bar 62332 disposed between the first clamping block and the second clamping block, when the adjusting nut is turned, the first clamp block 62322 moves towards each other on the first adjusting screw 62331 and the first clamp block 62323 on the second adjusting screw, the radioactive probe 2 is placed between the first clamp block 62322 and the first clamp block 62323, thereby achieving the function of fastening the radioactive probe 2, and the spring 62333 on the slide bar 62332 is in a compressed state; when the adjusting nut is rotated reversely outwards, the spring 62333 in a compressed state resets the first clamp block 62322 and the first clamp block 62323 under the action of tension, and then the clamp blocks are taken out;
further, the outer wall of the outer shell 62324 is further provided with a backing plate (a plurality of backing plates can be provided), and the backing plate is used for increasing the firmness of the outer shell 62324 in the clamp shell 6231, so that the box body 62 is firmer, and the service life of the box body 62 is prolonged.
In one embodiment, as shown in fig. 10, the casing 62324 includes a front panel (not shown), a rear panel (not shown), a left panel (not shown), a right panel (not shown), a second bottom panel (not shown), and a second cover 623242 with a circular hole; a cushion 623241 is arranged on the second bottom plate; one end of the radioactive probe 2 is arranged in the accommodating part through the round hole, and the bottom of the radioactive probe 2 is positioned on the cushion 623241; the first adjusting screw 62331 drives the first clamp block 62322 to attach to the radioactive probe 2, and the second adjusting screw drives the first clamp block 62323 to attach to the radioactive probe 2. Understandably, the front lining plate, the rear lining plate, the left lining plate, the right lining plate, the second bottom plate and the second cover plate 623242 enclose the outer shell 62324 and are detachably connected, so that the manufacturing cost and the maintenance cost of the nuclear power station burn-in test platform are reduced; the cushion 623241 serves as a cushion when the radiation probe 2 is mounted in the mounting portion of the case 62, i.e., serves as a layer of protection for the radiation probe 2.
The present invention is not limited to the above preferred embodiments, and any modifications, equivalent replacements, and improvements made within the spirit and principle of the present invention should be included in the protection scope of the present invention.

Claims (15)

1. The utility model provides a nuclear power station test platform that crashes which characterized in that includes: the device comprises an on-site processing unit, a radioactive probe, a remote display unit, a main body frame and a side wall outer plate; the side wall outer plate is enclosed into an accommodating space with an opening on the side surface, and the main body frame is arranged in the accommodating space;
the in-situ processing unit is connected to one side of the main body frame opposite to the side opening;
the main body frame is provided with a first drawer for installing the remote display unit, a second drawer for installing the radioactive probe and a third drawer for installing radioactive source substances; the first drawer, the second drawer and the third drawer are arranged in parallel; and a lifting platform for adjusting the distance between the radioactive source substance and the radioactive probe is arranged in the third drawer.
2. The nuclear power station burn-in test platform according to claim 1, wherein the first drawer is of a non-drawable structure, a first transparent open door is arranged on the side wall outer plate corresponding to the first drawer, and a second transparent open door is arranged on the side wall outer plate corresponding to the second drawer; the second drawer and the third drawer are both of drawable structures.
3. The nuclear power plant burn-in test platform according to claim 1, wherein a fourth drawer for storing tools is further arranged on the main body frame; the fourth drawer is of a drawable structure and is arranged in parallel with the first drawer.
4. The nuclear power plant burn-in test platform according to claim 3, wherein a first groove is further formed in the main body frame, and the nuclear power plant burn-in test platform further comprises an automatic rope winder installed in the groove.
5. The nuclear power station burn-in test platform according to claim 1, further comprising a first bottom plate connected to the bottom of the side wall outer plate, wherein a first roller is arranged on the first bottom plate; a reinforcing upright post vertical to the first bottom plate is arranged at the inner edge of the main body frame; and a first handle is arranged on the side wall outer plate.
6. The nuclear power station overlock test platform according to claim 1, wherein the main body frame comprises a shell, a transverse plate and a vertical plate, the transverse plate and the vertical plate are both mounted on the shell, the transverse plate is connected with the vertical plate, and an included angle between the transverse plate and the vertical plate is larger than 90 degrees.
7. The nuclear power plant burn-in test platform according to claim 6, wherein the vertical plate is provided with a slot and a baffle plate for limiting the installation position of the in-situ processing unit; the on-site processing unit is provided with an inserting plate and connected to the vertical plate through the inserting plate inserted into the inserting groove.
8. The nuclear power plant serger test platform as recited in claim 6, wherein said riser is provided with a wire guide hole, said main frame further comprises a wire guide tube disposed in said first drawer, one end of said wire guide tube being in communication with said wire guide hole, the other end of said wire guide tube being in communication with said second drawer.
9. The nuclear power station burn-in test platform according to claim 1, further comprising a lead chamber trolley detachably connected to the side wall outer plate;
the lead chamber trolley comprises a trolley body and a box body used for mounting the radioactive probe, and a second groove used for bearing the box body is formed in the trolley body; and the vehicle body is also provided with a second roller and a second handle.
10. The nuclear power plant serger test platform as recited in claim 9, wherein the box body comprises a first cover plate, a lead chamber body, a probe clamp and a telescopic rod; the telescopic rod is connected between the first cover plate and the lead chamber body, and the probe clamp is installed in the lead chamber body.
11. The nuclear power plant burn-in testing platform according to claim 10, wherein the lead chamber body includes a first lead chamber body, a second lead chamber body and a movable partition, the movable partition being disposed between the first lead chamber body and the second lead chamber body.
12. The nuclear power plant serger test platform as recited in claim 9, wherein the probe clamp includes a clamp housing, a clamp body and an adjustment assembly; the clamp body is arranged in the clamp shell and is provided with a containing part for fixing the radioactive probe; the fixture comprises a fixture shell, and is characterized in that a first adjusting hole is formed in the fixture shell, a second adjusting hole is formed in the fixture body, and the adjusting assembly penetrates through the first adjusting hole and the second adjusting hole and then extends into the accommodating part.
13. The nuclear power plant serger test platform as recited in claim 12, wherein the clamp body comprises a first clamp block, a second clamp block and a shell of which the outer wall is connected with the clamp shell; the accommodating part is formed by the first clamp block and the second clamp block;
the adjusting component comprises a first adjusting screw rod which penetrates through the first adjusting hole and is connected with the first clamp block through the second adjusting hole, and a second adjusting screw rod which penetrates through the first adjusting hole and is connected with the second clamp block through the second adjusting hole.
14. The nuclear power plant serger test platform as recited in claim 13, wherein a first sliding hole is formed in the first clamp block, and a second sliding hole is formed in the second clamp block at a position opposite to the first sliding hole; the adjusting component also comprises a sliding rod with two ends respectively inserted in the first sliding hole and the second sliding hole, and a spring sleeved on the sliding rod; the slide bar is connected with the first clamp block and the second clamp block in a sliding mode, and two ends of the spring are respectively abutted to the first clamp block and the second clamp block.
15. The nuclear power plant burn-in test platform according to claim 13, wherein the shell comprises a front liner, a rear liner, a left liner, a right liner, a second bottom plate and a second cover plate with a round hole; a cushion pad is arranged on the second bottom plate; one end of the radioactive probe penetrates through the round hole to be installed in the accommodating part, and the bottom of the radioactive probe is positioned on the buffer pad; the first adjusting screw rod drives the first clamp block to be attached to the radioactive probe, and the second adjusting screw rod drives the second clamp block to be attached to the radioactive probe.
CN201911243238.6A 2019-12-06 2019-12-06 Nuclear power station burn-in test platform Active CN111123346B (en)

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Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN203644402U (en) * 2013-12-13 2014-06-11 中广核核电运营有限公司 Logical circuit testing device for nuclear power plant reactor protection system
CN106483451A (en) * 2016-10-11 2017-03-08 广东核电合营有限公司 Million kilowatt nuclear power station radioactivity monitoring system processing unit test platform
CN106817869A (en) * 2017-02-27 2017-06-09 郑州云海信息技术有限公司 A kind of removable integrated testing platform
CN207752044U (en) * 2017-12-28 2018-08-21 深圳市利和兴股份有限公司 Customize integration test cabinet
CN207883331U (en) * 2017-11-27 2018-09-18 中核控制系统工程有限公司 A kind of fuel for nuclear power plant cladding integrity detection sobs suction cabinet online

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN203644402U (en) * 2013-12-13 2014-06-11 中广核核电运营有限公司 Logical circuit testing device for nuclear power plant reactor protection system
CN106483451A (en) * 2016-10-11 2017-03-08 广东核电合营有限公司 Million kilowatt nuclear power station radioactivity monitoring system processing unit test platform
CN106817869A (en) * 2017-02-27 2017-06-09 郑州云海信息技术有限公司 A kind of removable integrated testing platform
CN207883331U (en) * 2017-11-27 2018-09-18 中核控制系统工程有限公司 A kind of fuel for nuclear power plant cladding integrity detection sobs suction cabinet online
CN207752044U (en) * 2017-12-28 2018-08-21 深圳市利和兴股份有限公司 Customize integration test cabinet

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