CN111613360B - Tritium removing process and device for tritium-containing radioactive solid wet waste - Google Patents
Tritium removing process and device for tritium-containing radioactive solid wet waste Download PDFInfo
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- CN111613360B CN111613360B CN201910166748.1A CN201910166748A CN111613360B CN 111613360 B CN111613360 B CN 111613360B CN 201910166748 A CN201910166748 A CN 201910166748A CN 111613360 B CN111613360 B CN 111613360B
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- tritium
- wet waste
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- tritiated
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/06—Processing
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/20—Disposal of liquid waste
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/30—Processing
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- Engineering & Computer Science (AREA)
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- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Environmental & Geological Engineering (AREA)
- Processing Of Solid Wastes (AREA)
Abstract
The invention relates to a tritium removing process and a tritium removing device for tritium-containing radioactive solid wet waste, wherein the process comprises the steps of drying tritium-containing radioactive solid wet waste in an airtight space with tritium permeation prevention and tritium leakage prevention, and condensing and collecting dried moisture and tritium-containing gas; the device includes an airtight box, and the box top is equipped with the feed inlet of the wet waste material of radioactive solid, is equipped with the slide rail in the box, be equipped with the feed wagon on the slide rail, the feed wagon can receive the follow the wet waste material of radioactive solid that the feed inlet was sent into to the solid waste after will removing the tritium through the sealed door of box one side shifts to the box outside the bottom half is equipped with drying-machine and refrigerated dryer, still is equipped with exhaust apparatus on the box. The invention can remove tritiated water in tritium-containing wet waste and collect the tritiated water, prevent harmful gas from escaping into the environment in the treatment process, remotely operate, protect personnel safety and reliably store the waste for a long time.
Description
Technical Field
The invention belongs to a treatment technology of tritium-containing waste, and particularly relates to a tritium removing process and device of tritium-containing radioactive solid wet waste.
Background
Radioactive solid waste is one of the main wastes generated by the operation of nuclear power plants or other nuclear facilities. The particularity of tritiated waste makes this type of radioactive waste subject to special considerations in disposal. Tritium has extremely strong permeability and easy diffusivity, if tritium and tritiated water vapor leak to the environment can be harmful to the health of workers when handling solid waste of this kind, according to the report that IAEA promulgated, the harm of tritiated water to the human body is 10000 times of tritiated gas, can produce the wet waste containing tritiated water when nuclear facility maintenance or accident handling, so need special system of handling to dispose them.
Most of the prior published technical documents are introduced to a tritiation removal treatment method for tritium-containing water and a method for rapidly transferring and treating tritium-containing gas in a tritium system, and no document report is found in the tritium removal treatment aspect of tritium-containing solid wet waste.
Disclosure of Invention
The invention aims to provide a tritium removing process and a tritium removing device for tritium-containing radioactive solid wet waste, aiming at the problems that tritiated water liquid contained in tritium-containing wet waste can cause harm and corrosivity to workers, and the safety of the workers and the long-term reliable storage of the waste are ensured.
The technical scheme of the invention is as follows: a tritium removing process for tritium-containing radioactive solid wet waste comprises the following steps:
(S1) drying tritium-containing radioactive solid wet waste in an airtight space with tritium permeation prevention and tritium leakage prevention;
(S2) condensing the dried moisture and tritium-containing gas;
(S3) discharging the condensed tritiated water into a tritiated water collecting tank, and connecting tail gas into a tritium-containing tail gas treatment device;
(S4) removing the dried solid waste out of the airtight space.
The utility model provides a contain tritium removal device of wet wastes material of tritium radioactivity solid, includes a airtight box, and the box top is equipped with the feed inlet of the wet wastes material of radioactivity solid, is equipped with the slide rail in the box, be equipped with the feed wagon on the slide rail, the feed wagon can receive the follow the wet wastes material of radioactivity solid that the feed inlet was sent into to the solid wastes material after will removing the tritium through the sealing door of box one side shifts to the box outside the bottom half is equipped with drying-machine and freezing formula desiccator, still is equipped with exhaust apparatus on the box.
Further, the tritium removing device for the tritium-containing radioactive solid wet waste is characterized in that the inner wall of the box body is coated with an aluminum-aluminum oxide tritium permeation preventing coating.
Further, as above-mentioned tritium removal device of tritium-containing radioactive solid wet waste, wherein, negative pressure is kept in the box, and the exhaust pipe of the exhaust apparatus is provided with a pneumatic butterfly valve for realizing automatic sealing.
Further, as above-mentioned tritium removal device of tritium-containing radioactive solid wet waste, wherein, the feed inlet adopts nitrile rubber to seal, is equipped with the high-speed joint handle on the feed inlet.
Further, as above contain wet waste's of tritium radioactive solid detritiation device, wherein, the feeding car include the feeding basket, feeding basket bottom is equipped with the slip tray, feeding basket and slip tray wholly set up on the slide rail and can follow the slide rail and remove, the slide rail pass through the slide rail support with the bottom half is connected.
Furthermore, the feeding vehicle is connected with a propulsion cylinder, and the propulsion cylinder provides driving force to realize forward and backward movement.
Further, as above-mentioned remove tritium device of containing wet waste of tritium radioactive solid, wherein, slip tray connect the tray cylinder, can move along the little slide rail that sets up in the feeding vehicle bottom under the drive of tray cylinder, realize the switching of slip tray.
Further, according to the tritium removing device for the tritium-containing radioactive solid wet waste, a plurality of holes are formed in the feeding basket and the sliding tray, so that hot air in the box body can be in full contact with the tritium-containing radioactive solid wet waste conveniently.
Further, the tritium removing device for the tritium-containing radioactive solid wet waste is characterized in that a peep window and an access cover are further arranged on the box body.
The invention has the following beneficial effects: the tritium removing process and device for tritium-containing radioactive solid wet waste provided by the invention can remove tritiated water in the tritium-containing wet waste and collect the tritiated water, prevent harmful gas from escaping into the environment in the treatment process, realize remote operation, protect personnel safety and reliably store the waste for a long time. This device is handled 5kg wet wastes material that contains tritium, and it can reach complete drying to dry 120 minutes, and waste weight equals initial dry weight, measures box and tritiated water collection tank surface, does not find there to be tritium to ooze. According to the humidity measurement result of tail gas, the efficiency of condensing and removing tritium can reach 99%, the work place is monitored, tritium-containing gas diffusion is not found, the tritium-containing wet waste is effectively treated before compression, the generation of liquid in the compression and volume reduction process is avoided, tritiated water in the wet waste is removed, and meanwhile, the safety of operators is guaranteed.
Drawings
FIG. 1 is a schematic diagram of the general structure of a tritium removal device for tritium-containing radioactive solid wet waste in a specific embodiment of the invention;
FIG. 2 is a cross-sectional view of a tritium removal apparatus for tritium-containing radioactive solid wet waste in an embodiment of the present invention;
fig. 3 is a schematic structural view of a feeding vehicle in an embodiment of the present invention.
In the figure, 1, a box body, 2, a feeding vehicle, 3, a peep window, 4, a feeding port, 5, an access cover, 6, a propelling cylinder, 7, a pneumatic butterfly valve, 8, a dryer and a freezing dryer, 9, a feeding basket, 10, a slide rail bracket, 11, a slide rail, 12, a tray cylinder, 13, a sliding tray and 14, a small slide rail are arranged.
Detailed Description
The invention is described in detail below with reference to the figures and examples.
Aiming at the characteristics of tritium-containing radioactive solid wet waste, the invention provides a tritium removal process, which adopts a drying-condensing-collecting mode to remove tritiated water of the tritium-containing radioactive solid wet waste, and the process specifically comprises the following steps:
(S1) drying tritium-containing radioactive solid wet waste in an airtight space with tritium permeation prevention and tritium leakage prevention;
(S2) condensing the dried moisture and tritium-containing gas;
(S3) discharging the condensed tritiated water into a tritiated water collecting tank, and connecting tail gas into a tritium-containing tail gas treatment device;
(S4) removing the dried solid waste out of the airtight space.
In order to realize the process, the invention provides a tritium removing device for tritium-containing radioactive wet solid waste, which comprises a closed box body 1, wherein a feed inlet 4 for the radioactive wet solid waste is arranged above the box body 1, a slide rail is arranged in the box body, a feed vehicle 2 is arranged on the slide rail, the feed vehicle 2 can receive the radioactive wet solid waste fed from the feed inlet 4 and transfer the tritium-removed wet solid waste to the outside of the box body 1 through a sealing door at one side of the box body, a dryer and a freezing dryer 8 are arranged at the bottom of the box body 1, and an exhaust device is also arranged on the box body.
In this embodiment, the box body 1 is a welded closed box chamber, and the inner wall of the box chamber is coated with an aluminum-aluminum oxide tritium permeation-preventing coating, which is formed by spraying an aluminum layer, and oxidizing the aluminum layer to form an aluminum oxide layer on the surface. The box body is provided with a peep window 3, a feed port 4, an access cover 5 and other parts, and the main function is to provide a space with air tightness for the installation foundation of each part and the operation of drying and the like.
The function of the feed wagon 2 is to transfer the solid waste introduced into the feed wagon to the outside of the box through a sealed door on one side of the box and to unload it into a metal drum or other container below. As shown in fig. 3, the feeding vehicle includes a feeding basket 9 and a sliding tray 13, the sliding tray 13 is disposed at the bottom of the feeding basket 9, the feeding basket 9 and the sliding tray 13 are integrally disposed on a sliding rail 11 and can move along the sliding rail, in this embodiment, the feeding vehicle is driven by a driving force provided by a propelling cylinder 6 connected to the feeding vehicle to move forward and backward, the sliding rail 11 is connected to the bottom of the box 1 through a sliding rail bracket 10, and the propelling cylinder 6 can be a double-acting cylinder. The sliding tray 13 is designed to be of a structure capable of being opened and closed, the sliding tray 13 is connected with the tray cylinder 12 and can move along a small sliding rail 14 arranged at the bottom of the feeding vehicle 2 under the driving of the tray cylinder 12, and therefore the opening and closing of the sliding tray are achieved. When the feeding cart 2 moves to the outside of the cabinet 1, the sliding tray 13 is opened by the driving of the tray cylinder 12, thereby performing a function of discharging the solid wastes in the feeding basket.
The feeding basket 9 and the sliding tray 13 are provided with a plurality of round holes, so that the hot air at the bottom of the box body can be in full contact with the solid wet waste to be dried. The whole feeding vehicle is connected with the bottom of the box body through a sliding rail support. The cylinder is a driving component and can drive the whole feeding vehicle to move forward and the sliding tray to be opened and closed. The slide rail is a sliding support component of the feeding vehicle and the sliding tray, and a heavy-load linear guide rail is selected.
The peeping window 3 arranged on the box body is used for on-site observation of personnel during feeding and drying operations. It is mainly composed of window frame, press frame, toughened glass and sealing strip.
The feeding hole 4 arranged on the box body is used for feeding operation of equipment. The feed inlet 4 is provided with a quick connection handle, so that the operation time is reduced, and the working efficiency is improved. In addition, the feed inlet is sealed by nitrile rubber, negative pressure is kept in the box, the gas flow direction is from outside to inside during the operation of opening the cover, and the tritium-containing gas is prevented from leaking.
The box body is provided with the access cover 5, so that the maintenance and the maintenance of the equipment in the later period are facilitated, and the closed state is kept under the normal working condition.
And a pneumatic butterfly valve 7 for realizing automatic sealing is arranged on an exhaust pipe of the exhaust device, so that radioactive gas is prevented from leaking.
The dryer is arranged at the bottom of the box body and used for drying wet waste, and the wet waste is dried and circulated in the box body, so that tritium-containing gas is not diffused, and the requirement of next treatment is met.
Freezing formula desiccator is used for condensing the moisture that the wet waste material was dried out, condenses the tritium-containing gas in the box, and the condensate water is directly discharged into tritiated water collection tank, and the collection tank scribbles and prevents tritium infiltration coating, and tail gas inserts and contains tritium tail gas processing apparatus, further absorbs probably remaining tritium gas.
The working process of the device is as follows: after the feed port was opened, the solid wet waste was dropped into the feed basket and the feed port was closed. And opening a dryer to dry and tritium-remove the wet waste. And (4) introducing the dried tritiated water into a freezing dryer through a pipeline, and then condensing. After the tritiated water is completely dried, the air cylinder is pushed to push the feeding vehicle to move to the outside of the box body. After the feeding vehicle is in place, the tray cylinder acts to push the sliding tray to slide so as to open the bottom of the feeding basket, and the solid wastes in the feeding basket directly fall into the metal barrel below due to the action of gravity. Then, the sliding tray returns to the original position under the driving of the tray cylinder, and the feeding vehicle slides back to the interior of the box body under the driving of the propelling cylinder, so that the tritium removal and feeding operation of the wet waste is completed.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is intended to include such modifications and variations.
Claims (8)
1. A tritium removing process for tritium-containing radioactive solid wet waste comprises the following steps:
(S1) in an airtight space with tritium permeation prevention and tritium leakage prevention, drying tritium-containing radioactive solid wet waste by a dryer positioned at the bottom of the airtight space, circulating the dried tritium-containing gas in the airtight space, and coating an aluminum-aluminum oxide tritium permeation prevention coating on the inner wall of the airtight space, wherein an aluminum layer is sprayed firstly, and an aluminum oxide layer is formed on the surface of the aluminum layer after oxidation;
(S2) condensing the dried moisture and tritium-containing gas through a freezing dryer positioned at the bottom of the airtight space;
(S3) discharging the condensed tritiated water into a tritiated water collecting tank, and connecting tail gas into a tritium-containing tail gas treatment device;
(S4) removing the dried solid waste out of the airtight space.
2. A tritium removing device for tritium-containing radioactive solid wet waste for realizing the process of claim 1, which is characterized in that: including an airtight box, the box inner wall scribbles aluminium-aluminium oxide and prevents tritium permeation coating, and the box top is equipped with the feed inlet of the wet waste material of radioactivity solid, is equipped with the slide rail in the box, be equipped with the skip on the slide rail, the skip can receive the follow the wet waste material of radioactivity solid that the feed inlet was sent into to the solid waste material after will removing the tritium through the sealing door of box one side shifts to the box outside the bottom half is equipped with drying-machine and refrigerated dryer, still is equipped with exhaust apparatus on the box, keep the negative pressure in the box, be equipped with on exhaust apparatus's the blast pipe and be used for realizing self-sealing's pneumatic butterfly valve.
3. Tritiated-removing device for radioactive solid wet waste containing tritium, according to claim 2, characterized in that: the feed inlet is sealed by nitrile rubber, and a quick connection handle is arranged on the feed inlet.
4. Tritiated-removing device for radioactive solid wet waste containing tritium, according to claim 2, characterized in that: the feeding vehicle comprises a feeding basket, a sliding tray is arranged at the bottom of the feeding basket, the feeding basket and the sliding tray are integrally arranged on the sliding rail and can move along the sliding rail, and the sliding rail is connected with the bottom of the box body through a sliding rail support.
5. Tritiated-removing device for radioactive solid wet waste containing tritium, according to claim 4, characterized in that: the feeding vehicle is connected with a propelling cylinder, and the propelling cylinder provides driving force to realize forward and backward movement.
6. Tritiated-removing device for radioactive solid wet waste containing tritium, according to claim 4, characterized in that: the sliding tray is connected with the tray cylinder and can move along a small sliding rail arranged at the bottom of the feeding vehicle under the driving of the tray cylinder, so that the sliding tray can be opened and closed.
7. Tritiated-removing device for radioactive solid wet waste containing tritium, according to claim 4, characterized in that: the feeding basket and the sliding tray are provided with a plurality of holes, so that the hot air in the box body can be fully contacted with the tritium-containing radioactive solid wet waste.
8. Tritiated-removing device for radioactive solid wet waste containing tritium, according to claim 2, characterized in that: the box body is also provided with a peep window and an access cover.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910166748.1A CN111613360B (en) | 2019-03-05 | 2019-03-05 | Tritium removing process and device for tritium-containing radioactive solid wet waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
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| CN201910166748.1A CN111613360B (en) | 2019-03-05 | 2019-03-05 | Tritium removing process and device for tritium-containing radioactive solid wet waste |
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| CN111613360A CN111613360A (en) | 2020-09-01 |
| CN111613360B true CN111613360B (en) | 2022-10-28 |
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Citations (1)
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| CN107015266A (en) * | 2017-05-22 | 2017-08-04 | 中国原子能科学研究院 | A kind of calibration system and its scaling method of flow gas environment ion-chamber tritium concentration monitor |
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| CN207689440U (en) * | 2017-12-21 | 2018-08-03 | 中国原子能科学研究院 | The analytical equipment of trace impurity content in hydrogen isotope gas and/or helium |
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