CN214226535U - Automatic removing device for radioactive dirt in valve cavity - Google Patents
Automatic removing device for radioactive dirt in valve cavity Download PDFInfo
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- CN214226535U CN214226535U CN202022545407.6U CN202022545407U CN214226535U CN 214226535 U CN214226535 U CN 214226535U CN 202022545407 U CN202022545407 U CN 202022545407U CN 214226535 U CN214226535 U CN 214226535U
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Abstract
The utility model belongs to the technical field of the dirt in the valve chamber, in particular to an automatic removing device for the radioactive dirt in the valve chamber, which comprises a movable trolley, a filter, a fluid transmission pump, an mechanical arm and a communicating pipeline; the device can replace manual work to automatically remove radioactive substances, residual radioactive liquid and metal particles generated by grinding deposited in the valve cavity, reduce the radiation irradiation and pollution risks of personnel, improve the decontamination effect, reduce the radiation source item of a unit, reduce the generation amount of radioactive waste and improve the field work efficiency.
Description
Technical Field
The utility model belongs to the technical field of the inside filth of valve cavity, concretely relates to automatic remove device of valve cavity radioactive filth.
Background
At present, in the radioactive environment inside a nuclear power plant, the manual decontamination mode is generally adopted for removing radioactive dirt (solid and liquid) inside a valve chamber. And removing radioactive substances deposited in the valve cavity and metal particles generated by grinding the sealing surface of the valve seat by adopting a manual wiping mode, and cleaning the residual radioactive liquid in the valve cavity by adopting manual wiping or using a simple suction tool.
The existing decontamination mode has the following problems: (1) the dose rate in the valve cavity can reach dozens of mSv/h to hundreds of mSv/h, and decontamination personnel can be exposed to high radiation irradiation and pollution risks; (2) under the high radiation irradiation environment, the operation time must be strictly controlled, decontamination personnel can only simply wipe, and the decontamination effect is poor; (3) cleaning cloth and tools used in the decontamination process become high-dosage rate waste after being polluted, the amount of radioactive waste is increased, and the irradiation dosage of personnel can be further increased during waste collection and transportation; (4) the manual decontamination is difficult to remove stubborn dirt and metal particles, and the decontamination effect is poor.
During the overhaul period of a nuclear power plant, a large amount of valve disassembly and maintenance work needs to be carried out, and grinding of sealing surfaces inside a valve cavity or replacement of parts needs to be carried out on a part of valves. Due to the structural characteristics of the valve cavity and the arrangement condition of pipelines, radioactive substances and residual radioactive liquid with high dose rate (dozens of mSv/h to hundreds of mSv/h) are easy to deposit in the valve cavity, so that higher dose irradiation is caused to maintainers, and the development of maintenance work is influenced; on the other hand, the hardfacing layer of the valve sealing surface is mainly made of cobalt-containing alloy materials, such as Stellite6 alloy (the content of Co-59 element is 53.9%), EPRI (American electric research institute) research shows that grinding of the valve sealing surface can generate cobalt-containing metal particles with the size of 4-40 μm, the particles can keep a suspension state due to the movement of water molecules and can circulate in a loop of a nuclear power unit for a long time, the cobalt-containing (Co-59) metal particles can be activated by neutrons to generate Co-60 after entering a reactor core, and taking 40g of cobalt entering the loop system every year as an example, about 3200Ci of Co-60 can be generated after two cycles, so that the radiation source level of the nuclear power unit is continuously increased. Therefore, decontamination work must be performed on the interior of the valve cavity to remove radioactive residues deposited on the interior of the valve cavity, residual radioactive liquid, and cobalt (Co-59) -containing metal particles generated by grinding.
The problems of high risk of radiation irradiation and pollution, poor decontamination effect, increase of radioactive wastes, low working efficiency and the like exist in the development of manual decontamination work inside the valve cavity of the valve.
SUMMERY OF THE UTILITY MODEL
To above not enough, the utility model aims at providing an automatic remove device of valve cavity radioactive waste and method can replace the manual work to the valve cavity inside sedimentary radioactive substance, remain radioactive liquid and grind the metal particle that produces and carry out the automation and get rid of, reduce personnel's radiation and shine and pollution risk, improve decontamination effect, reduce unit radiation source item, reduce radioactive waste production volume, improve on-the-spot work efficiency.
The technical scheme of the utility model as follows:
an automatic radioactive dirt removing device for a valve chamber comprises a movable trolley, a filter, a fluid transmission pump, a mechanical arm and a communicating pipeline;
the filter and the filter shielding shell are arranged on the left side of the middle part of the movable trolley, the filter is arranged in the filter shielding shell, and a filter shielding shell cover plate is arranged on the upper part of the filter shielding shell;
a fluid transfer pump is arranged on the right side of the middle part of the movable trolley and is fixed in the movable trolley through a support; the filter is communicated with the fluid transfer pump through a pipeline c, and the right end of the pipeline c is connected with a sewage discharge outlet through a valve a;
a pipeline a is arranged above the inner part of the movable trolley, the upper end of the right side of the pipeline a is connected with a quick connector female connector a through a valve b, a tee joint a and a tee joint a are arranged in the middle of the pipeline a, the lower part of the tee joint a is connected with a pipeline c, the upper part of the tee joint b is communicated with a pipeline b, and the left end of the pipeline a is connected with the quick connector female connector b through a valve d;
the mechanical arm base is fixed on the left side of the top of the movable trolley, the mechanical arm is fixed at the upper end of the mechanical arm base, a pipeline b is arranged inside the mechanical arm and the mechanical arm base, a valve c is arranged on the lower portion of the pipeline b, and an irradiation-resistant camera and a quick-acting joint female joint c are arranged at the front end of the mechanical arm.
The quick connector female joint c at the front end of the mechanical arm is connected with the quick connector male joint a at the top of the water absorption, dust absorption and cleaning head, and the lower end of the water absorption, dust absorption and cleaning head is provided with an opening.
The quick connector female joint c at the front end of the mechanical arm is connected with the quick connector male joint b at the top of the scrubbing and decontaminating head, the middle part of the scrubbing and decontaminating head is provided with an ultrasonic generator, and the lower part of the scrubbing and decontaminating head is provided with a hairbrush.
The brush can be detached and replaced.
The bottom of the movable trolley is provided with a guide wheel.
The cover plate of the filter shielding shell is an openable cover plate.
The mechanical arm is a degree of freedom mechanical arm.
The beneficial effects of the utility model reside in that:
utilize valve chamber radioactive waste automatic removal device to replace the manual work to develop the inside decontamination work of valve pocket, can effectively reduce decontamination personnel and maintenance personal radiation dose, promote decontamination effect and decontamination efficiency, get rid of the radioactive waste in the valve pocket and grind the metal particle that produces, reduce maintenance personal irradiated dose and reduce unit radiation source item, reduce radioactive waste production volume and radioactive waste and shine to staff's radiation simultaneously, specifically as follows:
(1) the automatic radioactive dirt removing device for the valve cavity replaces a person to carry out decontamination work inside the valve cavity, decontamination is automatically carried out after a decontamination worker completes equipment installation near a valve to be decontaminated, the decontamination worker remotely monitors a decontamination process through a camera, radiation irradiation dose of the decontamination worker is obviously reduced, and the decontamination worker is prevented from being irradiated by higher dose in the decontamination process;
(2) the automatic radioactive dirt removing device for the valve cavity can perform decontamination operation for a long time, various decontamination heads are used for performing targeted decontamination on different parts (including the bottom of the valve cavity and the sealing surface of the valve seat) and different radioactive substances (including solid and liquid radioactive substances), the decontamination effect and the decontamination efficiency are obviously improved, the problems that the decontamination time is limited (personnel operation time must be limited under a high-radiation environment) and the decontamination effect is poor and the decontamination efficiency is low due to the fact that only cleaning cloth and other simple manners are used for decontamination in the conventional manual decontamination manner are solved, the irradiation dose of valve maintenance personnel is reduced by reducing the radiation level in the valve cavity through high-efficiency decontamination, and meanwhile, cobalt (Co-59) containing metal particles generated by grinding the valve seat are removed, so that the situation that the metal particles are activated by a reactor core to increase the radiation source item of a unit is avoided;
(3) the automatic valve chamber radioactive dirt removing device utilizes the built-in filter to filter solid and liquid radioactive substances, and a radiation shielding device is arranged on the filter, so that the consumption of materials such as the existing manual decontamination cloth is avoided, the generation amount of radioactive waste is reduced, and the radiation irradiation of the radioactive waste to other workers is reduced.
Drawings
FIG. 1 is a schematic structural view of an automatic radioactive contaminant remover for a valve chamber according to the present invention;
in the figure: 1. a guide wheel of the movable trolley; 2. moving the trolley; 3. a support; 4. a sewage draining outlet; 5. a valve a; 6. a fluid transfer pump; 7. a valve b; 8. a quick connector female connector a; 9. a filter shield housing cover plate; 10. a pipeline a; 11. a tee joint a; 12. a tee joint b; 13. a pipe b; 14. a mechanical arm; 15. a mechanical arm base; 16. a valve c; 17. a valve d; 18. a quick connector female connector b; 19. a camera; 20. a quick connector female connector c; 21. a quick connector male connector a; 22. a water absorption dust absorption and removal head; 23. a quick connector male connector b; 24. brushing and cleaning the decontamination head; 25. an ultrasonic generator; 26. a brush; 27. a pipe c; 28. a filter; 29. the filter shields the housing.
Detailed Description
The technical solutions in the embodiments of the present invention will be described clearly and completely with reference to the accompanying drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only some embodiments of the present invention, not all embodiments. Based on the embodiments in the present invention, all other embodiments obtained by a person skilled in the art without creative work belong to the protection scope of the present invention.
In the automatic radioactive dirt removing device for the valve chamber shown in fig. 1, the guide wheel 1 is arranged at the bottom of the movable trolley 2, the filter 28 and the filter shielding shell 29 are arranged on the left side of the middle of the movable trolley, the filter 28 is arranged inside the filter shielding shell 29, the filter shielding shell cover plate 9 is arranged at the upper part of the filter shielding shell 29, and the filter shielding shell cover plate 9 is an openable cover plate;
a fluid transfer pump 6 is arranged on the right side of the middle part of the movable trolley 2, and the fluid transfer pump 6 is fixed inside the movable trolley 2 through a support 3; the filter 28 is communicated with the fluid transfer pump 6 through a pipeline c27, and the right end of the pipeline c27 is connected with the sewage outlet 4 through a valve a 5;
a pipeline a10 is arranged above the inner part of the movable trolley 2, the upper end of the right side of the pipeline a10 is connected with a quick connector female joint a8 through a valve b7, a tee joint a11 and a tee joint a12 are arranged in the middle of the pipeline a10, the lower part of the tee joint a11 is connected with a pipeline c27, the upper part of the tee joint b12 is communicated with the pipeline b13, and the left end of the pipeline a10 is connected with a quick connector female joint b18 through a valve d 17;
the mechanical arm base 15 is fixed on the left side of the top of the movable trolley 1, the mechanical arm 14 is a 5-degree-of-freedom mechanical arm and is fixed at the upper end of the mechanical arm base 15, a pipeline b13 is arranged inside the mechanical arm 14 and the mechanical arm base 15, a valve c16 is arranged at the lower part of a pipeline b13, and an irradiation-resistant camera 19 and a quick-coupling female joint c20 are arranged at the front end of the mechanical arm 14;
the male connector a21 of the quick connector at the top of the water absorption, dust collection and cleaning head 22 can be connected with the female connector c20 of the quick connector at the front end of the mechanical arm 14, and the lower end of the water absorption, dust collection and cleaning head 22 is an opening;
the male joint b23 of the quick connector at the top of the scrubbing and cleaning head 24 can be connected with the female joint c20 of the quick connector at the front end of the mechanical arm 14, the ultrasonic generator 25 is arranged at the middle part of the scrubbing and cleaning head 24, the brush 26 is arranged at the lower part of the scrubbing and cleaning head 24, and the brush 26 can be detached and replaced.
Correspondingly, the utility model discloses well decontamination plant's application method as follows:
1) after the valve gap was opened and taken away to the maintainer with the valve flange, the decontamination personnel will the utility model discloses an automatic remove device of valve chamber radioactivity filth removes near waiting to decontaminate the valve, arrange the waste liquid collecting vessel in drain 4 exit, close valve a7, valve c17, open valve a5, valve b16, connect the dust absorption decontamination head 22 that absorbs water to quick-operation joint female joint 20 of arm 14 front end at most through quick-operation joint male joint 21, start fluid transfer pump 6, the decontamination personnel carries out the automatic dust absorption procedure a that absorbs water of valve pocket that sets for in advance on long-range centralized control platform (not drawn in the figure), the radioactivity solid of clearance valve pocket bottom, the liquid mixture, the radioactivity solid, the liquid mixture is along the dust absorption decontamination head 22 that absorbs water, pipeline b13, tee bend b12, pipeline c27, filter 28, fluid transfer pump 6, arrange outside drain 4. The radioactive solid-liquid mixture at the bottom of the valve cavity is cleaned, so that the radiation level in the valve cavity is reduced, and a waterless environment is created for the follow-up valve clack dismantling work of maintenance personnel.
2) After the automatic water and dust suction procedure a of the valve cavity is finished, a decontamination worker moves the automatic radioactive dirt removing device of the valve cavity to a position far away from the valve, after a maintenance worker removes the valve clack, the decontamination worker moves the automatic radioactive dirt removing device of the valve cavity to a position close to the valve, the decontamination worker remotely controls the mechanical arm 14, observes the dirt condition in the valve cavity through the irradiation camera 20, connects the scrubbing and decontamination head 24 to the quick connector female joint c20 at the front end of the mechanical arm 14 through the quick connector male joint b23, starts the ultrasonic generator 25, executes the automatic scrubbing and decontamination procedure b of the valve cavity on the remote centralized control console, executes the automatic water and dust suction procedure a of the valve cavity in the step 1) again, cleans the residual dirt after decontamination of the valve cavity, and further reduces the radiation level in the valve cavity, the irradiated dose of subsequent maintenance personnel for carrying out valve grinding work is reduced.
3) After the valve cavity automatic scrubbing and decontaminating procedure b and the second valve cavity automatic water absorbing and dust collecting procedure a are finished, the decontamination personnel moves the automatic radioactive dirt removing device of the valve cavity to the position far away from the valve, and after the maintenance personnel grind the sealing surface of the valve seat, the decontamination personnel moves the automatic radioactive dirt removing device of the valve cavity of the utility model to the position close to the valve, a clean brush 26 is replaced, the scrubbing decontamination head 24 is connected to the quick connector female joint c20 at the front end of the mechanical arm 14 through the quick connector male joint b23, the ultrasonic generator 25 is started, the decontamination personnel executes the automatic cleaning decontamination procedure c of the sealing surface of the valve seat on the remote centralized control console, and executing the automatic water and dust absorption procedure a of the valve cavity in the step 1) again to clean the metal particles on the surface of the sealing surface of the valve seat and avoid the metal particles from being activated by the reactor core subsequently.
4) The decontamination personnel monitors the decontamination condition on a remote centralized control console by using an irradiation-resistant camera 19 at the front end of the mechanical arm 14, and if abnormity is found, emergency operation is carried out to stop decontamination work.
5) For the situation that the internal structure of the valve cavity is complex or the automatic decontamination program is not thoroughly decontaminated, a decontamination worker controls the mechanical arm 14 on a remote centralized control console to carry out remote control decontamination, and simultaneously observes the decontamination condition through the radiation-resistant camera 19 at the front end of the mechanical arm 14. In addition, when automatic decontamination is difficult to perform due to limited space of the valve installation position and small valve size, a decontamination worker communicates the water absorption, dust collection and decontamination head 22 with the quick connector female connector 18 by using a hose with a quick connector male connector and a quick connector female connector respectively arranged at two ends, closes the valve b8 and the valve c16, opens the valve a5 and the valve d17, then starts the fluid transmission pump 6, holds the water absorption, dust collection and decontamination head 22 by hand to perform manual water absorption, dust collection and decontamination, and holds the decontamination head 24 by hand to perform manual scrubbing and decontamination.
6) In the decontamination process of the valve cavity, radioactive substances may be deposited in the pipeline and the valve of the automatic radioactive sewage removing device for the valve cavity, the relevant pipeline and the valve can be washed for decontamination, and the specific method is as follows:
opening a valve a5, a valve b7, closing a valve c16 and a valve d17, connecting an external flushing pipeline with a quick connector male connector to a quick connector female connector a8, and flushing and decontaminating a pipeline a10, a pipeline c27, a filter 28, a fluid transfer pump 6 and a valve a 5;
opening a valve b7 and a valve c16, closing a valve a5 and a valve d17, connecting an external flushing pipeline with a quick connector male connector to a quick connector female connector a8, and flushing and decontaminating the pipeline a10, the pipeline b13 and the valve c 16;
opening the valve b7 and the valve d17, closing the valve a5 and the valve c16, connecting an external flushing pipeline with a quick connector male connector to the quick connector female connector a8, and flushing and decontaminating the pipeline a10 and the valve d 17.
In the drawings of the disclosed embodiments of the present invention, only the methods related to the disclosed embodiments are referred to, and other methods can refer to the general design, and under the condition of no conflict, the same embodiment and different embodiments of the present invention can be combined with each other;
the above description is only for the preferred embodiment of the present invention and should not be taken as limiting the invention, and any modifications, equivalent replacements, improvements, etc. made within the spirit and principle of the present invention should be included in the protection scope of the present invention.
Claims (7)
1. An automatic radioactive dirt removing device for a valve chamber comprises a movable trolley, a filter, a fluid transmission pump, a mechanical arm and a communicating pipeline;
the method is characterized in that: the filter and the filter shielding shell are arranged on the left side of the middle part of the movable trolley, the filter is arranged in the filter shielding shell, and a filter shielding shell cover plate is arranged on the upper part of the filter shielding shell;
a fluid transfer pump is arranged on the right side of the middle part of the movable trolley and is fixed in the movable trolley through a support; the filter is communicated with the fluid transfer pump through a pipeline c, and the right end of the pipeline c is connected with a sewage discharge outlet through a valve a;
a pipeline a is arranged above the inner part of the movable trolley, the upper end of the right side of the pipeline a is connected with a quick connector female connector a through a valve b, a tee joint a and a tee joint a are arranged in the middle of the pipeline a, the lower part of the tee joint a is connected with a pipeline c, the upper part of the tee joint b is communicated with a pipeline b, and the left end of the pipeline a is connected with the quick connector female connector b through a valve d;
the mechanical arm base is fixed on the left side of the top of the movable trolley, the mechanical arm is fixed at the upper end of the mechanical arm base, a pipeline b is arranged inside the mechanical arm and the mechanical arm base, a valve c is arranged on the lower portion of the pipeline b, and an irradiation-resistant camera and a quick-acting joint female joint c are arranged at the front end of the mechanical arm.
2. The automatic valve chamber radioactive contamination removing device according to claim 1, wherein: the quick connector female joint c at the front end of the mechanical arm is connected with the quick connector male joint a at the top of the water absorption, dust absorption and cleaning head, and the lower end of the water absorption, dust absorption and cleaning head is provided with an opening.
3. The automatic valve chamber radioactive contamination removing device according to claim 1, wherein: the quick connector female joint c at the front end of the mechanical arm is connected with the quick connector male joint b at the top of the scrubbing and decontaminating head, the middle part of the scrubbing and decontaminating head is provided with an ultrasonic generator, and the lower part of the scrubbing and decontaminating head is provided with a hairbrush.
4. An automatic valve chamber radioactive contamination removing device according to claim 3, wherein: the brush can be detached and replaced.
5. An automatic valve chamber radioactive contamination removing device according to any one of claims 1 to 4, wherein: the bottom of the movable trolley is provided with a guide wheel.
6. An automatic valve chamber radioactive contamination removing device according to any one of claims 1 to 4, wherein: the cover plate of the filter shielding shell is an openable cover plate.
7. An automatic valve chamber radioactive contamination removing device according to any one of claims 1 to 4, wherein: the mechanical arm is a degree of freedom mechanical arm.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202022545407.6U CN214226535U (en) | 2020-11-06 | 2020-11-06 | Automatic removing device for radioactive dirt in valve cavity |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202022545407.6U CN214226535U (en) | 2020-11-06 | 2020-11-06 | Automatic removing device for radioactive dirt in valve cavity |
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| CN214226535U true CN214226535U (en) | 2021-09-17 |
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| CN202022545407.6U Active CN214226535U (en) | 2020-11-06 | 2020-11-06 | Automatic removing device for radioactive dirt in valve cavity |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112366018A (en) * | 2020-11-06 | 2021-02-12 | 福建福清核电有限公司 | Automatic valve chamber radioactive dirt removing device and method |
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- 2020-11-06 CN CN202022545407.6U patent/CN214226535U/en active Active
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112366018A (en) * | 2020-11-06 | 2021-02-12 | 福建福清核电有限公司 | Automatic valve chamber radioactive dirt removing device and method |
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