JPH0820558B2 - Waste liquid storage device - Google Patents

Description

DETAILED DESCRIPTION OF THE INVENTION Object of the Invention (Industrial field of application) The present invention relates to a waste liquid storage device that stores a waste liquid mixed with a solid precipitate in a stirrable manner, and is particularly discharged from a nuclear power generation facility. The present invention relates to a waste liquid storage device that stores and agitates a chemically active radioactive waste liquid (a highly corrosive waste liquid).

(Prior Art) A nuclear power plant is equipped with a radioactive liquid waste treatment facility, and by this facility, the radioactive liquid waste generated at the power plant is treated and safely managed. Radioactive waste liquid is generated from equipment drain water from various equipment, waste powder resin generated from condensate demineralizer, etc., waste resin generated from ion exchange resin of condensate demineralizer, etc. It is concentrated waste liquid or clad water that is generated. These radioactive waste liquids are collected in the radioactive waste liquid storage device housed in the building of the nuclear power generation facility and temporarily held.

Ion exchange resin, clad, and other relatively small solid particles are mixed in the radioactive waste liquid.When these solid particles are stored as radioactive waste liquid, they settle in the storage container of the radioactive waste liquid treatment device, and Deposited on the bottom. The radioactive waste liquid stored in the storage container is transferred to a regenerator for the purpose of reuse and subjected to chemical treatment such as filtration or desalting. However, in order to transfer the radioactive waste liquid to the regenerator, it is necessary to stir in advance in the storage container to cause the precipitate to rise and to mix the precipitate with the supernatant waste liquid (mother liquor). Therefore, a stirrer is installed in the radioactive waste liquid treatment apparatus, and the stirrer stirs the stored radioactive waste liquid.

Various types of mechanisms of this stirring device are adopted.
For example, by immersing the entire stirring pump or only its propeller part in the bottom of the storage container and directly stirring the radioactive waste liquid by a motor drive, or by installing the stirring pump device outside the storage container, The one that jets the discharge liquid jet toward the bottom of the storage container to stir the precipitate, etc. is put to practical use. As an example of the latter waste liquid storage device having a stirring function, there is a device disclosed in JP-A-61-83999.

Such a conventional apparatus has an advantage that the precipitate at the bottom of the storage container can be efficiently stirred without installing any dynamic stirring mechanism in the storage container, but It also has some drawbacks.

That is, since no consideration is given to disassembling the double pipe portion at the bottom of the storage container, it is difficult to check the corrosion and wear conditions of the wetted portion of the double pipe portion, and the inner pipe may be replaced. Can not.

Further, in the annular flow path constituted by the outer pipe and the inner pipe, that is, in the portion that changes the direction of the liquid flow at a substantially right angle, the liquid line changes abruptly, so that the pressure loss increases. When the pressure loss becomes extremely large, it is possible that eddy current causes harmful vibration and cavitation erosion in this vicinity.

Furthermore, since the inner pipe opens vertically to the bottom of the container, it is easy to entrain air in the inner pipe due to the suction vortex flow,
Therefore, there is a possibility that the pump performance is adversely affected. In order to remove this harmful effect on the pump performance, it is necessary to keep the stirring stop liquid level high in the storage container, but this reduces the actual capacity (effective capacity) of the waste liquid storage device ( In other words, it may increase the invalid storage capacity).

Therefore, in Japanese Patent Application No. 63-265669 relating to the earlier application of the present applicant, in the waste liquid storage device, inside the outer pipe that guides the pump pressurized liquid from the stirring pump to the injection guide element,
The inner pipe that guides the waste liquid in the storage container to the agitation pump is housed to form a double pipe structure, and the inner pipe is detachably housed in the outer pipe, so that the inner pipe can be removed during maintenance and inspection of the device. The inspection and maintenance of the liquid contact part of the double pipe part consisting of the inner and outer pipes and the replacement of the inner pipe can be easily performed, and the maintenance and inspection of the device can be carried out efficiently.
The waste liquid storage device according to the previous application is used to store “chemically inactive radioactive waste liquid (weak liquid with weak corrosiveness)” in a radioactive liquid waste treatment facility of a nuclear power plant.

However, for the following reasons, the storage of "chemically active radioactive waste liquid (strong corrosive waste liquid)" such as 25% sodium sulfate solution that regenerates the ion exchange resin used for various water purification systems in power plants Has not been adopted by.

That is, since the mounting bolt is used when attaching the injection guide element that is joined to the upper end of the inner pipe to the bottom of the storage container, the screw hole for that will locally reduce the wall thickness of the storage container, and the strength of the container. Cause a decrease in There is a possibility that crevice corrosion will occur between the mounting bolt and its screw hole. In that case, the female screw of the screw hole will be damaged, so it is not possible to simply replace the mounting bolt for repair. So either replace the entire reservoir or
Or it becomes necessary to perform major repairs including weld overlay processing,
Container life is reduced. The mounting bolt cannot be made large in order to reduce the fluid resistance when stirring the waste liquid, but this reduces the seismic strength.

(Problems to be Solved by the Invention) As described above, in the waste liquid storage device of the previous application, there are drawbacks such as a reduction in life due to crevice corrosion of the screw holes of the mounting bolts and a reduction in stirring resistance due to the fluid resistance of the mounting bolts. is there.

This invention was made in consideration of the above circumstances,
The liquid tight boundary (liquid tight boundary member) of the storage container can be screwed or a jetting / suction guide element can be attached to the storage container without using mounting bolts, resulting in good stirring efficiency and easy maintenance / inspection. A waste liquid storage device is provided.

(Structure of the Invention) (Means for Solving the Problems) The present invention relates to a storage container for storing waste liquid such as radioactive waste liquid, and an injection guide element having a jet port radially arranged on the bottom of the storage container. And a stirring pump arranged outside the storage container, wherein one end is connected to the bottom of the storage container and the other end is connected to the discharge pipe of the stirring pump. An outer pipe that guides the liquid to the injection guide element, and a detachable housing that is detachably accommodated in the outer pipe, is connected to the injection guide element, and stores the waste liquid stored in the storage container in the pump suction pipe of the stirring pump. An inner pipe for guiding connection, a suction guide element communicating with the inner side of the inner pipe and integrally formed with the injection guide element, and the inner pipe are detachably attached to the bottom of the storage container. A plurality of guide vanes that are radially welded and fixed to each other, a small hole formed in an upper portion of the suction guide element, and a gap formed between a lower end portion of the inner pipe and the outer pipe. It is characterized by that.

(Operation) Therefore, according to the waste liquid storage device of the present invention,
An inner pipe for guiding the waste liquid in the storage container to the stirring pump is housed inside the outer pipe that guides the pump pressurized liquid from the stirring pump to the injection guide element, and this inner pipe is provided at the bottom of the storage container. Since it is detachably accommodated in the outer pipe by the guide vanes, the inner pipe is removed during maintenance / inspection of the device to check and maintain the liquid contact part of the double pipe part consisting of the inner and outer pipes, and replace the inner pipe. Etc. can be easily performed, and the injection guide element is not directly fixed to the bottom of the container with a mounting screw, so that the stirring efficiency of the waste liquid is also improved.

Also, since a small hole is formed in the upper part of the suction guide element,
Even if waste liquid remains on the upper outside of the suction guide element, this waste liquid can be guided into the suction guide element through a small hole,
During internal inspection, all waste liquid stored in the storage container can be completely discharged. Further, by forming the small hole, it is possible to crush the vortex generated near the center of the inside of the suction guide element when the waste liquid is concentrated from the entire circumference in the horizontal direction of the suction guide element during the normal operation.

Furthermore, since a gap is formed between the lower end of the inner pipe and the outer pipe, even if waste liquid stays between the inner pipe and the outer pipe,
This waste liquid can be completely discharged from the gap.

Embodiment An embodiment of the present invention will be described below with reference to the drawings.

2 is an overall sectional view showing a first embodiment of a waste liquid storage device according to the present invention, FIG. 1 is an enlarged sectional view of an essential part of FIG. 2, and FIG. 3 is a sectional view taken along line III-III of FIG. is there.

The waste liquid storage device 1 has a storage container 3 housed in a concrete skeleton 2 of a nuclear power generation facility building. The storage container 3 is a cylindrical storage tank, and is supported in a storage chamber 4 of the concrete skeleton 2 via a support skirt 5. The support skirt 5 is provided on the floor 6 of the storage chamber 4.
Will be erected on. The bottom surface of the storage container 3 is formed into a smooth curved surface, and the outer pipe 7 shown in FIG. 1 is liquid-tightly connected to the storage container 3 near the center of the bottom by welding or the like.

The top part of the outer pipe 7 opens into the storage container 3, while the inner pipe 8 is inserted near the center of the cross section of the pipe to form a double pipe structure. The lower end of the outer tube 7 is in the shape of a sphere that is one step larger than the others, and a branch port 10 is formed in the sphere 9 in the horizontal direction. The branch port 10 is connected to the pump discharge pipe 11 by welding or the like. Outer tube 7 including bulb 9
An annular channel 12 is formed by being surrounded by the inner tube 8 and the inner tube 8. In this annular flow path 12, the flow direction of the pump pressurized liquid from the pump discharge pipe 11 is converted into a substantially right angle.

Further, the spherical portion 9 of the outer tube 7 is vertically downwardly branched into the branch port 13
Is formed. A connection pipe 14 is connected to the branch port 13 by welding or the like. As shown in FIG. 2, the connection pipe 14 is bifurcated near the floor surface 6, and a pump suction pipe 15 and a transfer pipe 16 are connected to each branch pipe.

On the other hand, as shown in FIG. 1, the inner pipe 8 ends immediately before protruding from the top of the outer pipe 7, and opens to the storage container 3. An injection guide element 17 is connected to the end of the inner tube 8 and covers the top opening of the outer tube 7 at a distance. The jet guide element 17 has an inverted dish shape or an umbrella disk shape, and a plurality of radial guide blades 18 are provided on the lower surface in the circumferential direction. The vane 18 has a height effective for guiding the fluid, and maintains a distance with the storage container 3 that does not cause crevice corrosion. By such an injection guide element 17,
The top portion of the outer pipe 7 is closed in the axial direction and is opened over the entire circumference in the circumferential direction. An annular ejection port 20 is formed between the bottom of the storage container 3 and the outer peripheral edge of the ejection guide element 17.

A suction guide element 21 is integrally formed with the injection guide element 17 at the upper end of the inner pipe 8. The suction guide element 21 is in the shape of an inverted hat and has a suction port 24 that is open all around the horizontal direction. In addition, a plurality of suction guide elements 21 (third
Four suction guide vanes 23 are provided. Further, a small hole 25 is formed at the top of the suction guide element 21,
The waste liquid in the storage container 3 is provided so as to directly flow into the suction guide element 21 through the small hole 25.

FIG. 4 is an enlarged view of IV portion in FIG. 3, and FIG. 5 is V- in FIG.
It is a V sectional view. Injection guide element 17 connected to the inner tube 8
And a suction guide vane integrally formed with the suction guide element 21.
23 is extended and protruded outside the outer diameter of the suction guide element 21,
It is detachably and firmly fixed to the upper part of the guide vane 32 by an eye plate 30 and through bolts 31 (eight blades in FIG. 4) which are superposed on the suction guide vanes 23 from both sides. The guide vanes 32 are radially arranged outside the injection guide element 17 at equal intervals (four in FIG. 5) and are welded to the bottom of the storage container 3.

The lower end 26 of the inner pipe 8 is formed in a truncated hollow conical shape,
It is fitted into the lower portion of the spherical portion 9 of the outer tube 7. The outer diameter of the lower end portion 26 of the inner pipe 8 is set to be slightly smaller than the inner diameter of the lower portion of the spherical portion 9, and there is a gap between the lower end portion 26 and the lower portion of the spherical portion 9.
27 is formed. The lower end 26 of the inner tube 8 is downwardly tapered and has a truncated hollow conical shape so that the inner tube 8 can be easily mounted from the inside of the storage container 3 into the outer tube 7.

On the other hand, as shown in FIG. 2, the pump suction pipe 15 connected to one side of the communication pipe 14 is connected to the suction port of the stirring pump 28. Also, at the discharge port of the stirring pump 28, the pump discharge pipe
11 is connected, and this pump discharge pipe 11 is connected to the branch port 10 of the outer pipe 7 via the valve 29.

The stirring pump 28 is driven by the pump motor 28A. The stirring pump 28, the pump suction pipe 15, and the pump discharge pipe 11 constitute a stirring pump device 30.

On the other hand, the transfer pipe 16 connected to the other side of the communication pipe 14,
It is connected to the suction port of the transfer pump 36. This transfer pump 36
A regeneration device 33 is connected to the discharge port of the above through a regeneration pipe 32. By this regenerating device 33, the radioactive waste liquid in the storage container 3 is subjected to chemical treatment such as filtration and desalting. A valve 34 is installed in the regeneration pipe 32. The transfer pump 36 is driven by a pump motor 36A.

 Next, the operation will be described.

A radioactive waste liquid such as device drain water discharged from various devices installed in the nuclear power generation facility is guided to and stored in the storage container 3 of the waste liquid storage device 1. When the radioactive waste liquid is stored, minute solids such as ion exchange resin and clad are deposited and deposited on the bottom of the storage container 3. When a predetermined amount of radioactive waste liquid is stored in the storage container 3, the waste liquid is transferred to the regenerator 33 for chemical treatment such as filtration and desalting. However, when the deposit is deposited on the bottom of the storage container 3, the radioactive waste liquid cannot be directly transferred to the regenerator 33. In this case, therefore, the transfer pump 36 is stopped and the valve 34 is closed. Then, the stirring pump 28 is started. At this time, the valve 29 is also kept open.

When the stirring pump 28 is started, the supernatant waste liquid (mother liquor) of the radioactive waste liquid stored in the storage container 3 passes from the suction guide element 21 of the waste liquid storage device 1 through the inside pipe 8, and the communication pipe 14 and the pump suction pipe. It is sucked into the stirring pump 28 via 15. This supernatant waste liquid is pressurized by the agitation pump 28, and is discharged to the spherical portion 9 of the outer pipe 7 through the pump discharge pipe 11. The flow of the supernatant liquid waste discharged into the spherical portion 9 is converted into a substantially right angle, rises through the annular flow path 12, is guided by the radial guide vanes 18 of the injection guide element 17, and the flow direction is changed. It is converted to a substantially right angle again. Then, the supernatant waste liquid is radially ejected from the entire circumference of the annular ejection port 20 of the ejection guide element 17 so as to crawl on the bottom surface of the storage container 3.

The supernatant waste liquid jetted from the annular jet port 20 flows along the bottom surface of the storage container 3 to stir the precipitate and stir it to mix it. This jet flow induces an entrained flow 35 that is several times the pump discharge flow rate. These jets and entrained flow 35 flow in the radial direction to reach the side wall surface of the storage container 3,
Since a huge upward flow rises from this side wall surface,
An annular flow occurs in a torus shape inside the storage container 3, effectively stirring the precipitate throughout the container,
It can be mixed.

When the agitation of the precipitate is completed in the storage container 3 and the radioactive waste liquid is uniformly agitated and mixed, the transfer pump 36 is activated and the valve 34 is opened. By starting the transfer pump 36,
The radioactive waste liquid in the storage container 3 passes through the suction guide element 21 and the inner pipe 8, as well as the connecting pipe 14 and the transfer pipe 16,
The pressure is increased by the transfer pump 36. The pressurized radioactive waste liquid is sent to the regenerator 33 through the regenerator pipe 32, where it is chemically treated. Although the operation of the stirring pump 28 may be stopped when the transfer pump 36 is started, it is more efficient to keep the operation of the stirring pump 28 by opening the valve 29.

By the way, when the inside of the storage container 3 is inspected, it is necessary to completely discharge the radioactive waste liquid stored in the storage container 3. At this time, if the radioactive waste liquid is retained in the annular flow path 12 of the outer pipe 7, it becomes impossible to completely discharge the radioactive waste liquid.

However, in this embodiment, the radioactive waste liquid in the annular flow path 12 is fed to the gap between the lower end portion 26 of the inner pipe 8 and the spherical portion 9 of the outer pipe 7.
Since it can flow from 27 to the branch port 13 side provided vertically below the outer pipe 7, the radioactive waste liquid in the storage container 3 can be completely discharged. The flow of radioactive waste liquid through the gap 27 occurs even during normal stirring operation, but the stirring pump
By setting an appropriate gap size from the capacity of 28, a practical reduction in stirring efficiency can be ignored.

Further, in this embodiment, if the through bolt 31 is loosened, the eye plate 30 is removed, and the suction guide vane 23 is removed from the guide vane 32,
Since the entire inner pipe 8 combined with the integrally formed suction guide vane 23, suction guide element 21 and injection guide element 17 can be disassembled from the storage container 3, the double pipe portion consisting of the inner pipe 8 and the outer pipe 7 is connected. Corrosion and wear conditions that have occurred in the liquid part can be checked and repaired. At the same time, if desired, the integrally formed suction guide element 21, injection guide element 17 and inner tube 8 can be replaced.

Further, in the double pipe portion of the outer pipe 7 and the inner pipe 8, that is, in the annular flow path 12 that changes the direction of the liquid flow at a substantially right angle, one stage below the outer pipe 7 is provided below the outer pipe 7. Since the large spherical portion 9 is provided, the flow velocity is reduced in the spherical portion 9, and the disturbance of the streamline can be prevented. As a result, it is possible to reduce the pressure loss in the double pipe portion and suppress the generation of harmful vibration and cavitation caused by the vortex flow.

Further, since the suction guide element 21 is mounted on the upper end of the inner pipe 8 and the suction port 24 is opened over the entire circumference in the horizontal direction, the radioactive waste liquid can be dispersed and sucked from the entire circumference in the horizontal direction. Further, since the suction guide vanes 23 are extended in the outer diameter direction for the convenience of attachment to the guide vanes 32, the suction guide element is flattened accordingly. Therefore, even if the liquid level of the radioactive waste liquid in the storage container 3 is lowered, air is not sucked into the inner pipe 8 by the suction vortex flow, and the stirring pump 28
It does not adversely affect the pump performance and life of the.
Therefore, the stirring stop liquid level in the storage container 3 can be set as low as possible just near the upper end of the suction guide element 21, so that even if the storage container 3 has the same shape and size as the conventional one,
The actual capacity (effective capacity) of the storage container 3 can be increased.

In addition to this, in the present invention, unlike the previous application, the injection guide element 17 coupled to the inner pipe 8 is not fixed to the storage container with the mounting bolt, so the bottom portion of the storage container 3 is fixed by the screw hole for the mounting bolt. There is no local metal loss that leads to a decrease in strength. Further, even when the corrosive waste liquid is stored, crevice corrosion does not occur in the screw hole for the mounting bolt and the life of the entire container is not shortened. The bolt 31 itself that connects the guide vanes 32 and the suction guide vanes 23 and the clearance in the vicinity thereof do not cause crevice corrosion during high-speed stirring because high-speed fluid always passes through, but crevice corrosion may also occur when stirring is stopped. is there. However, since these parts can be easily repaired, this corrosion does not cause a leak accident by immersing the liquid-tight boundary of the storage container 3.

In the present invention, the guide vanes 32 and the suction guide vanes 2
3, the number of fixing elements of the eye plate 30 and the bolt 31 can be arbitrarily selected, but these do not increase the fluid resistance unlike the mounting bolt in the above-mentioned previous application. Rather, the guide vanes 32 arranged outside the injection guide element 17 exert a rectifying effect and improve the stirring efficiency.

Further, in the present invention, the guide vanes 32 and the suction guide vanes
If the bolts 31 for connecting the 23 are replaced by through bolts, even if crevice corrosion occurs in the screw, the pair may be replaced. Further, with such a coupling structure, not only the bolt 31 but also a portion where crevice corrosion is likely to occur can be made of a corrosion resistant alloy.

In the present invention, since the injection guide element 17 and the suction guide element 21 are integrated, the places where crevice corrosion occurs are reduced,
And handling is also convenient.

Further, since the small hole 25 is formed in the upper part of the suction guide element 21, even if the radioactive waste liquid remains outside the upper part of the suction guide element 21, this waste liquid can be guided into the suction guide element 21 through the small hole 25. At the time of internal inspection, all radioactive waste liquid stored in the storage container 3 can be completely discharged.

Further, this small hole 25, during normal operation of the stirring pump device 30, when the radioactive waste liquid is concentrated from the entire circumference of the suction port 24 of the suction guide element 21 in the horizontal direction, a vortex flow generated near the center of the inside of the suction guide element 21. Effective for crushing.

Further, since the lower end portion of the inner pipe 8 has a truncated hollow conical shape, the inner pipe 8 can be easily inserted into the outer pipe 7 and the streamline in the lower portion of the spherical portion 9 of the outer pipe 7 can be reduced. Disturbance can also be reduced.

Further, although a temperature difference occurs between the inner pipe 8 and the outer pipe 7 due to changes in operating conditions and the surrounding atmosphere, since the inner pipe 8 can freely expand and contract in the axial direction, thermal stress is applied to the inner pipe 8 and the outer pipe 7. Does not occur.

Further, since the stirring pump 28 is provided on the floor 6 of the storage chamber 4 and is not installed in the storage container 3, the stirring pump 28 can be easily maintained and inspected, and no special pump specifications are required. Therefore, the pump pressure can be increased and the pump can be downsized. Further, since electric equipment such as a motor is not disposed in the radioactive waste liquid, it is possible to effectively prevent an electric shock accident of a worker and at the same time prevent electrical corrosion of the storage container 3.

In addition, since the stirring pump 28, the pump motor 28A, etc. are fixed to the floor surface 6 of the storage chamber 4, it is possible to improve the earthquake resistance and radiation resistance of the constituent materials of the waste liquid storage device 1, and to provide a strong radioactivity. Even waste liquid can be safely stirred.

In addition, although the case where the bottom surface of the storage container 3 is a spherical self-supporting tank having a spherical shape has been described in the above-described embodiment, the same effect can be exhibited even with a lining container in which a metal lining plate is lined on a concrete skeleton.

Further, although the above-described embodiment is the case of the nuclear power generation facility, the present invention is not limited to the nuclear power generation facility, and is not limited to power generation, other nuclear power related facilities, or a general general non-nuclear power or radioactivity related Applicable to facilities.

〔The invention's effect〕

According to the present invention, the inner pipe for guiding the waste liquid in the storage container to the stirring pump is housed inside the outer pipe that guides the pump pressurizing liquid from the stirring pump to the injection guide element, and is provided at the bottom of the container. Since the inner pipe is detachably accommodated in the outer pipe by the guide vanes, the inner pipe can be removed during maintenance and inspection of the device to easily inspect and repair the condition of corrosion and wear of the wetted part, and if necessary. Since the inner tube can be easily replaced, maintenance and inspection of the device can be efficiently performed. Furthermore, the chemically active waste liquid can be stored in the liquid-tight boundary of the container without causing crevice corrosion.

Also, since a small hole is formed in the upper part of the suction guide element,
Even if waste liquid remains on the upper outside of the suction guide element, this waste liquid can be guided into the suction guide element through a small hole,
During internal inspection, all waste liquid stored in the storage container can be completely discharged. Further, by forming the small holes, when the waste liquid is concentrated from the entire circumference in the horizontal direction of the suction guide element during normal operation, it is possible to crush the vortex generated near the inner center of the suction guide element, and to prevent harmful vibration and cavitation. Occurrence can be prevented.

Furthermore, since a gap is formed between the lower end of the inner pipe and the outer pipe, even if waste liquid stays between the inner pipe and the outer pipe,
This waste liquid can be completely discharged from the gap.

Therefore, it is possible to completely discharge all the waste liquid stored in the storage container at the time of internal inspection.Therefore, even if the waste liquid is a radioactive waste liquid with strong radioactivity, there is no possibility of being exposed to workers, and the work efficiency is improved. Can be improved.

[Brief description of drawings]

FIG. 1 is an enlarged sectional view of an essential part of FIG. 2, FIG. 2 is an entire sectional view showing a first embodiment of a waste liquid storage device according to the present invention, and FIG.
1 is a sectional view taken along the line III-III of FIG. 1, FIG. 4 is an enlarged view of a portion IV in FIG. 3, and FIG. 5 is a sectional view taken along line VV of FIG. 1 ... Waste liquid storage device, 3 ... Storage container, 7 ... Outer pipe,
8 ... Inner pipe, 11 ... Pump discharge pipe, 12 ... Annular flow passage, 15 ... Pump suction pipe, 17 ... Injection guide element, 20
...... Spout port, 21 …… Suction guide element, 23 …… Suction guide vane, 24 …… Suction port, 28 …… Stirring pump, 30 …… Plate, 31
...... Bolt, 32 ...... Information vane.

Claims (1)

[Claims] 1. A storage container for storing waste liquid such as radioactive waste liquid, an injection guide element arranged at the bottom of the storage container and having radial ejection ports, and a stirring pump arranged outside the storage container. In the waste liquid storage device having, one end is connected to the bottom of the storage container and the other end is connected to the discharge pipe of the stirring pump, and an outer pipe for guiding the discharge liquid of the pump to the injection guide element, An inner pipe that is detachably accommodated in the outer pipe, is connected to the injection guide element, and guides and connects the waste liquid stored in the storage container to the pump suction pipe of the stirring pump; and the inner pipe. A plurality of guide vanes that are in communication with each other and that the suction guide element integrally formed with the injection guide element and the inner tube are detachably attached and that are radially welded and fixed to the bottom of the storage container. When the eyelet upper portion formed of the suction guide element, the waste liquid chamber device being characterized in that a gap formed between the outer tube and the lower end of the inner tube.