CN214312677U - Nuclide treatment waste liquid storage system - Google Patents
Nuclide treatment waste liquid storage system Download PDFInfo
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- CN214312677U CN214312677U CN202023342446.2U CN202023342446U CN214312677U CN 214312677 U CN214312677 U CN 214312677U CN 202023342446 U CN202023342446 U CN 202023342446U CN 214312677 U CN214312677 U CN 214312677U
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Abstract
The application discloses nuclide treatment waste liquid storage system includes: the waste liquid inlet main pipe is respectively connected with a first inlet of the waste liquid tank through a waste liquid inlet branch pipe; the waste liquid discharge main pipe is respectively connected with a first outlet of the waste liquid tank through a waste liquid discharge branch pipe, the waste liquid introduction branch pipe is provided with a first switch element, and the waste liquid discharge branch pipe is provided with a second switch element. Therefore, the technical problems that radioactive substances in the waste liquid can not be completely decayed and then discharged when the nuclide treatment waste liquid is treated in the prior art, and the discharged waste liquid can cause environmental pollution are solved.
Description
Technical Field
The application relates to the technical field of environmental protection, in particular to a nuclide treatment waste liquid storage system.
Background
Some radioactive nuclides can release alpha rays or beta rays and the like in the decay process, have stronger ionizing radiation effect, and have stronger killing effect on tumor cells or abnormal proliferation tissues and the like. Nuclide treatment means that radionuclide with therapeutic effect, such as iodine-131, strontium-89, yttrium-90, lutetium-177, radium-223 and other nuclides or labeled drugs, iodine-125 particles, phosphorus-32 application patches and the like are utilized to kill diseased cells and tissues accurately in a close range so as to achieve the purpose of treatment. The waste liquid after the nuclide treatment has radioactivity, and the radioactive substances in the waste liquid can not be completely decayed and then discharged when the nuclide treatment waste liquid is treated in the prior art, so that the discharged waste liquid can cause environmental pollution.
Aiming at the technical problems that radioactive substances in the waste liquid can not be completely decayed and then discharged when the nuclide treatment waste liquid is treated in the prior art, and the discharged waste liquid can cause environmental pollution, an effective solution is not provided at present.
SUMMERY OF THE UTILITY MODEL
The utility model provides a nuclide treatment waste liquid storage system to at least, solve exist among the prior art when carrying out nuclide treatment waste liquid treatment, can not realize discharging after the complete decay of the radioactive substance in the waste liquid, the waste liquid after the emission can cause environmental pollution's technical problem.
According to an aspect of the present application, there is provided a nuclide therapy waste storage system comprising: the waste liquid inlet main pipe is respectively connected with a first inlet of the waste liquid tank through a waste liquid inlet branch pipe; the waste liquid discharge main pipe is respectively connected with a first outlet of the waste liquid tank through a waste liquid discharge branch pipe, the waste liquid introduction branch pipe is provided with a first switch element, and the waste liquid discharge branch pipe is provided with a second switch element.
Optionally, a controller is further included, communicatively coupled to the first switching element and the second switching element.
Optionally, the waste liquid tank is provided with a first liquid level meter, wherein the first liquid level meter is arranged at a height corresponding to a preset maximum liquid storage amount of the waste liquid tank, and the liquid level meter is in communication connection with the controller.
Optionally, a timer corresponding to the waste liquid tank is further included, and the timer is in communication with the controller.
Optionally, the system further comprises a clean water leading-in main pipe, wherein the clean water leading-in main pipe is connected with the second inlet of the waste liquid tank through a clean water leading-in branch pipe, the clean water leading-in branch pipe is provided with a third switching element, and the third switching element is in communication connection with the controller.
Optionally, a second level gauge is disposed in the waste liquid tank, the second level gauge is disposed at a position close to the bottom of the waste liquid tank, and the second level gauge is in communication with the controller.
Optionally, the waste liquid tank is further provided with an alarm and a third liquid level meter located above the first liquid level meter, and the alarm and the third liquid level meter are in communication connection with the controller.
Optionally, the device further comprises a sampling main pipe connected with the sampling port, the sampling main pipe is connected with the second outlet of the waste liquid tank through a sampling branch pipe, the sampling branch pipe is provided with a fourth switch element, and the fourth switch element is in communication connection with the controller.
The utility model provides a nuclide treatment waste liquid storage system, which comprises a plurality of waste liquid tanks, a waste liquid leading-in main pipe and a waste liquid discharging main pipe. The waste liquid can flow into the waste liquid guiding branch pipe through the waste liquid guiding main pipe, and then flows into the waste liquid tank through the first inlet of the waste liquid tank through the waste liquid guiding branch pipe. Because the utility model provides a nuclide treatment waste liquid storage system has four waste liquid jars, and one of them waste liquid jar can be filled with earlier to the waste liquid, continues to pour into the waste liquid to another waste liquid jar again. After the waste liquid jar is filled with to the waste liquid, along with the lapse of time, radioactive substance in the waste liquid can decay and accomplish, and the waste liquid flows into waste liquid discharge branch pipe through the first export of waste liquid jar, and last waste liquid discharge branch pipe is responsible for the leading-in waste liquid discharge of waste liquid, and the waste liquid discharge is responsible for the waste liquid discharge after will decay. And the technical problems that radioactive substances in the waste liquid can not be completely decayed and then discharged when the nuclide treatment waste liquid is treated in the prior art, and the discharged waste liquid can cause environmental pollution are solved.
The above and other objects, advantages and features of the present invention will become more apparent to those skilled in the art from the following detailed description of specific embodiments thereof, taken in conjunction with the accompanying drawings.
Drawings
Some specific embodiments of the present application will be described in detail hereinafter by way of illustration and not limitation with reference to the accompanying drawings. The same reference numbers in the drawings identify the same or similar elements or components. Those skilled in the art will appreciate that the drawings are not necessarily drawn to scale. In the drawings:
FIG. 1 is a schematic diagram of a nuclide therapy waste storage system arrangement according to one embodiment of the present application.
Detailed Description
It should be noted that, in the present invention, the embodiments and features of the embodiments may be combined with each other without conflict. The present invention will be described in detail below with reference to the accompanying drawings in conjunction with embodiments.
In order to make the technical solution of the present invention better understood, the technical solution of the embodiments of the present invention will be clearly and completely described below 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 efforts shall belong to the protection scope of the present invention.
It should be noted that the terms "first," "second," and the like in the description and claims of the present invention and in the drawings described above are used for distinguishing between similar elements and not necessarily for describing a particular sequential or chronological order. It is to be understood that the terms so used are interchangeable under appropriate circumstances for describing embodiments of the invention herein. Furthermore, the terms "comprises," "comprising," and "having," and any variations thereof, are intended to cover a non-exclusive inclusion, such that a process, method, system, article, or apparatus that comprises a list of steps or elements is not necessarily limited to those steps or elements expressly listed, but may include other steps or elements not expressly listed or inherent to such process, method, article, or apparatus.
It is noted that the terminology used herein is for the purpose of describing particular embodiments only and is not intended to be limiting of example embodiments according to the present application. As used herein, the singular forms "a", "an" and "the" are intended to include the plural forms as well, and it should be understood that when the terms "comprises" and/or "comprising" are used in this specification, they specify the presence of stated features, steps, operations, devices, components, and/or combinations thereof, unless the context clearly indicates otherwise.
Referring to fig. 1, the utility model provides a nuclide treatment waste liquid storage system, including: a plurality of waste liquid tanks 110, 120, 130, 140, a waste liquid introduction main pipe 200, and a waste liquid discharge main pipe 400, wherein the waste liquid introduction main pipe 200 is connected to the first inlets 114, 124, 134, 144 of the waste liquid tanks 110, 120, 130, 140 through waste liquid introduction branch pipes 210, 220, 230, 240, respectively; the waste liquid discharge main pipe 400 is connected to the first outlets 116, 126, 136, 146 of the waste liquid tanks 110, 120, 130, 140 through waste liquid discharge branch pipes 410, 420, 430, 440, respectively, and the waste liquid introduction branch pipes 210, 220, 230, 240 are provided with first opening and closing members 211, 221, 231, 241, and the waste liquid discharge branch pipes 410, 420, 430, 440 are provided with second opening and closing members 411, 421, 431, 441.
As described in the background art, the waste liquid after nuclide treatment is radioactive, in the prior art, when the nuclide treatment waste liquid is treated, the radioactive substances in the waste liquid cannot be completely decayed and then discharged, and the discharged waste liquid causes environmental pollution.
To solve the problems in the prior art, the utility model provides a nuclide therapy waste liquid storage system, as shown in fig. 1. The nuclide treatment waste liquid storage system includes a plurality of waste liquid tanks 110, 120, 130, 140, a waste liquid introduction main pipe 200, and a waste liquid discharge main pipe 400. After the nuclide therapy in the hospital, the waste liquid for the nuclide therapy is introduced from the waste liquid introduction main pipe 200, and the waste liquid can flow into the waste liquid introduction branch pipes 210, 220, 230, and 240 through the waste liquid introduction main pipe 200, and then flow into the waste liquid tanks through the first inlets 114, 124, 134, and 144 of the waste liquid tanks 110, 120, 130, and 140 through the waste liquid introduction branch pipes 210, 220, 230, and 240. Because the utility model provides a nuclide treatment waste liquid storage system has four waste liquid jars, and one of them waste liquid jar can be filled with earlier to the waste liquid, continues to pour into the waste liquid to another waste liquid jar again. After the waste liquid tank is filled with the waste liquid, radioactive substances in the waste liquid are completely decayed with the passage of time, the waste liquid flows into the waste liquid discharge branch pipes 410, 420, 430 and 440 through the first outlets 116, 126, 136 and 146 of the waste liquid tank 110, 120, 130 and 140, finally the waste liquid discharge branch pipes 410, 420, 430 and 440 guide the waste liquid into the waste liquid discharge main pipe 400, and the waste liquid discharge main pipe 400 discharges the decayed waste liquid. And the technical problems that radioactive substances in the waste liquid can not be completely decayed and then discharged when the nuclide treatment waste liquid is treated in the prior art, and the discharged waste liquid can cause environmental pollution are solved.
Optionally, a controller is further included, communicatively connected to the first switching elements 211, 221, 231, 241 and the second switching elements 411, 421, 431, 441. When it is necessary to control the flow of the waste liquid in the waste liquid introduction branch pipes 210, 220, 230, 240 and the flow of the waste liquid in the waste liquid discharge branch pipes 410, 420, 430, 440, a worker can control the first switching elements 211, 221, 231, 241 and the second switching elements 411, 421, 431, 441 by using a controller, and the operation is convenient.
Optionally, the waste liquid tank 110, 120, 130, 140 is provided with a first level gauge 112, 122, 132, 142, wherein the first level gauge 112, 122, 132, 142 is provided at a height corresponding to a preset maximum storage amount of the waste liquid tank 110, 120, 130, 140 and the level gauge is in communication connection with the controller. When the waste liquid in the waste liquid tank reaches the height corresponding to the preset maximum liquid storage amount, the operator can stop the inflow of the waste liquid through the controller. The first level gauge 112, 122, 132, 142 may prevent the waste fluid from exceeding a preset maximum storage volume.
Optionally, a timer corresponding to the waste liquid tank 110, 120, 130, 140 is further included, and the timer is in communication with the controller. The timer corresponding to the waste liquid tanks 110, 120, 130, 140 can count the number of days of the waste liquid in the waste liquid tank, and when the time of the waste liquid in the waste liquid tank reaches ninety days, the radioactive substance in the waste liquid tank can decay and finish, thereby achieving the purpose of safe discharge.
Optionally, a clean water introduction main pipe 300 is further included, wherein the clean water introduction main pipe 300 is connected with the second inlets 115, 125, 135, 145 of the waste liquid tanks 110, 120, 130, 140 through clean water introduction branch pipes 310, 320, 330, 340, the clean water introduction branch pipes 310, 320, 330, 340 are provided with third switch elements 311, 321, 331, 341, and wherein the third switch elements 311, 321, 331, 341 are in communication connection with the controller. After the waste liquid is discharged, the clean water can flow into the clean water introduction branch pipes 310, 320, 330 and 340 through the clean water introduction main pipe 300, and then flow into the waste liquid tank through the second inlets 115, 125, 135 and 145 of the waste liquid tanks 110, 120, 130 and 140, so as to clean the waste liquid tank, thereby ensuring the sanitation and safety of the waste liquid tank.
Optionally, a second level gauge 113, 123, 133, 143 is disposed within the waste liquid tank 110, 120, 130, 140, the second level gauge 113, 123, 133, 143 is disposed proximate a bottom of the waste liquid tank 110, 120, 130, 140, and the second level gauge 113, 123, 133, 143 is in communication with the controller. When the waste liquid in the waste liquid tank reaches the height of the second liquid level meter in the waste liquid tank, the completion of the discharge of the waste liquid in the waste liquid tank is indicated.
Optionally, the waste liquid tank 110, 120, 130, 140 is further provided with an alarm and a third level gauge 111, 121, 131, 141 above the first level gauge 112, 122, 132, 142, and the alarm and the third level gauge 111, 121, 131, 141 are in communication with the controller. When the waste liquid in the waste liquid tanks 110, 120, 130 and 140 reaches the positions of the third liquid level meters 111, 121, 131 and 141, the waste liquid is indicated to exceed the preset maximum liquid storage amount, at this time, the alarm can give an alarm, and the worker can control the waste liquid tanks through the controller, so that the overflow of the waste liquid is avoided.
Optionally, a sampling main pipe 500 connected with the sampling port is further included, the sampling main pipe 500 is connected with the second outlet 117, 127, 137, 147 of the waste liquid tank 110, 120, 130, 140 through a sampling branch pipe 510, 520, 530, 540, the sampling branch pipe 510, 520, 530, 540 is provided with a fourth switching element 511, 521, 531, 541, and wherein the fourth switching element 511, 521, 531, 541 is in communication connection with the controller. The waste liquid can also flow into the sampling branch pipes 510, 520, 530, 540 through the second outlets 117, 127, 137, 147 of the waste liquid tanks 110, 120, 130, 140, and further into the sampling main pipe 500. The staff can be in the person in charge of taking a sample 500 of going on the sample to the waste liquid to be convenient for the staff to carry out further detection to the radioactive substance in the waste liquid.
Unless specifically stated otherwise, the relative arrangement of the components and steps, the numerical expressions, and numerical values set forth in these embodiments do not limit the scope of the present invention. Meanwhile, it should be understood that the sizes of the respective portions shown in the drawings are not drawn in an actual proportional relationship for the convenience of description. Techniques, methods, and apparatus known to those of ordinary skill in the relevant art may not be discussed in detail but are intended to be part of the specification where appropriate. In all examples shown and discussed herein, any particular value should be construed as merely illustrative, and not limiting. Thus, other examples of the exemplary embodiments may have different values. It should be noted that: like reference numbers and letters refer to like items in the following figures, and thus, once an item is defined in one figure, further discussion thereof is not required in subsequent figures.
Spatially relative terms, such as "above … …," "above … …," "above … …," "above," and the like, may be used herein for ease of description to describe one device or feature's spatial relationship to another device or feature as illustrated in the figures. It will be understood that the spatially relative terms are intended to encompass different orientations of the device in use or operation in addition to the orientation depicted in the figures. For example, if a device in the figures is turned over, devices described as "above" or "on" other devices or configurations would then be oriented "below" or "under" the other devices or configurations. Thus, the exemplary term "above … …" can include both an orientation of "above … …" and "below … …". The device may be otherwise variously oriented (rotated 90 degrees or at other orientations) and the spatially relative descriptors used herein interpreted accordingly.
In the description of the present invention, it should be understood that the orientation or positional relationship indicated by the orientation words such as "front, back, up, down, left, right", "horizontal, vertical, horizontal" and "top, bottom" etc. are usually based on the orientation or positional relationship shown in the drawings, and are only for convenience of description and simplification of description, and in the case of not making a contrary explanation, these orientation words do not indicate and imply that the device or element referred to must have a specific orientation or be constructed and operated in a specific orientation, and therefore, should not be interpreted as limiting the scope of the present invention; the terms "inner and outer" refer to the inner and outer relative to the profile of the respective component itself.
The above description is only for the preferred embodiment of the present application, but the scope of the present application is not limited thereto, and any changes or substitutions that can be easily conceived by those skilled in the art within the technical scope of the present application should be covered within the scope of the present application. Therefore, the protection scope of the present application shall be subject to the protection scope of the claims.
Claims (8)
1. A nuclide therapy waste fluid storage system, comprising: a plurality of waste liquid tanks (110, 120, 130, 140), a waste liquid introduction main pipe (200) and a waste liquid discharge main pipe (400), wherein
The waste liquid introduction main pipe (200) is connected to the first inlets (114, 124, 134, 144) of the waste liquid tanks (110, 120, 130, 140) through waste liquid introduction branch pipes (210, 220, 230, 240), respectively;
the main waste liquid discharge pipe (400) is connected to the first outlets (116, 126, 136, 146) of the waste liquid tanks (110, 120, 130, 140) through waste liquid discharge branch pipes (410, 420, 430, 440), respectively, and
the waste liquid introduction branch pipe (210, 220, 230, 240) is provided with a first opening and closing member (211, 221, 231, 241), and the waste liquid discharge branch pipe (410, 420, 430, 440) is provided with a second opening and closing member (411, 421, 431, 441).
2. The nuclide therapy waste fluid storage system as in claim 1, further comprising a controller communicatively coupled to the first switching element (211, 221, 231, 241) and the second switching element (411, 421, 431, 441).
3. Nuclide therapy waste fluid storage system according to claim 2, wherein the waste fluid tank (110, 120, 130, 140) is provided with a first level gauge (112, 122, 132, 142), wherein the first level gauge (112, 122, 132, 142) is provided at a height corresponding to a preset maximum liquid storage volume of the waste fluid tank (110, 120, 130, 140), and wherein the level gauge is in communication with the controller.
4. The nuclide therapy waste fluid storage system as in claim 2, further comprising a timer corresponding to the waste fluid tank (110, 120, 130, 140) and in communication with the controller.
5. The nuclide treatment waste liquid storage system as in claim 2, further comprising a clear water introduction main pipe (300), wherein
The main clean water inlet pipe (300) is connected to the second inlet (115, 125, 135, 145) of the waste liquid tank (110, 120, 130, 140) via a clean water inlet branch pipe (310, 320, 330, 340), the clean water inlet branch pipe (310, 320, 330, 340) is provided with a third switching element (311, 321, 331, 341), and the third switching element (311, 321, 331, 341) is connected to the controller in a communication manner.
6. A nuclide therapeutic waste storage system as defined in claim 4 wherein a second level gauge (113, 123, 133, 143) is disposed within the waste tank (110, 120, 130, 140), the second level gauge (113, 123, 133, 143) is disposed proximate a bottom of the waste tank (110, 120, 130, 140), and the second level gauge (113, 123, 133, 143) is in communication with the controller.
7. A nuclide therapeutic waste storage system as claimed in claim 3, wherein the waste tank (110, 120, 130, 140) is further provided with an alarm and a third level gauge (111, 121, 131, 141) located above the first level gauge (112, 122, 132, 142), and the alarm and the third level gauge (111, 121, 131, 141) are in communication with the controller.
8. Nuclide therapy waste liquid storage system according to claim 2, further comprising a main sampling pipe (500) connected to a sampling port, said main sampling pipe (500) being connected to the second outlet (117, 127, 137, 147) of the waste liquid tank (110, 120, 130, 140) through a branch sampling pipe (510, 520, 530, 540), said branch sampling pipe (510, 520, 530, 540) being provided with a fourth switching element (511, 521, 531, 541), and wherein said fourth switching element (511, 521, 531, 541) is in communication with said controller.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202023342446.2U CN214312677U (en) | 2020-12-31 | 2020-12-31 | Nuclide treatment waste liquid storage system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202023342446.2U CN214312677U (en) | 2020-12-31 | 2020-12-31 | Nuclide treatment waste liquid storage system |
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| Publication Number | Publication Date |
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| CN214312677U true CN214312677U (en) | 2021-09-28 |
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| CN202023342446.2U Active CN214312677U (en) | 2020-12-31 | 2020-12-31 | Nuclide treatment waste liquid storage system |
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