JPH0631836B2 - Radioactive waste separation device - Google Patents

Description

TECHNICAL FIELD The present invention relates to a radioactive waste separation device for separating radioactive waste from gas.

[Conventional technology]

Generally, radioactive waste generated from nuclear power plants, etc.
It is roughly classified into three types: gas, liquid and solid, and the radioactivity is classified into high level, medium level and low level.

BACKGROUND ART Conventionally, among low-level solid wastes, combustible materials are incinerated and then the ash is stored in drums.

However, as the amount of solid waste increases, a large amount of ash is generated after the incineration process, and the storage amount is increasing year by year. Therefore, the above-mentioned process naturally has its limit.

Therefore, the treatment of the solid waste (incineration ash) using microwaves is disclosed in, for example, JP-A-55-1433.
No. 80 publication.

The radioactive waste processed by these microwave melting devices is a so-called incineration ash obtained by temporarily incinerating the radioactive waste discharged from a nuclear power plant or the like.

The incinerated ash is stored in drums and transported to the treatment plant. At the treatment plant, the incinerated ash is pneumatically transported from the drum, the air and the incinerated ash are separated using a cyclone, a filter (cloth, paper, etc.), the incinerated ash is stored in the hopper, and supplied to the feeder as needed. ing.

[Problems to be solved by the invention]

However, in the method as described above, since a cyclone, cloth or paper filter is used as a means for separating air and incinerator ash, the separation efficiency is low, and when the air is discharged to the outside, the separated air is separated. Need to be filtered again.

[Object of the Invention]

The present invention solves the above problems, and an object of the present invention is to provide a radioactive waste separation device capable of obtaining sufficient separation efficiency of radioactive waste from gas.

[Means for solving problems]

A radioactive waste separating apparatus according to the present invention is a rotary filter comprising a supply means for supplying powdery radioactive waste together with a gas into a container body, and a cylindrical porous body arranged in the container body. And suction means for sucking gas that has passed from the outer periphery of the rotary filter toward the inner periphery, and the radioactive waste that is arranged at a constant interval on the outer periphery of the rotary filter and adheres to the outer periphery of the rotary filter. And a separation plate for scraping off.

[Operation of the invention]

In the present invention, the radioactive waste in the form of powder or granules is supplied to the inside of the container main body together with the gas as the transfer fluid, and then is provided on the outer periphery of the rotary filter made of a cylindrical porous body arranged in the container main body. When they adhere to each other and have a certain thickness, they are scraped off by a separation plate arranged at a constant interval on the outer periphery of the rotary filter. The radioactive waste scraped off is dropped from the lower part of the container body into a hopper or the like. On the other hand, the gas that has passed through the porous body of the rotary filter is sucked by the suction means and discharged to the outside.

Example of Invention

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

FIG. 1 shows an embodiment of the radioactive waste separating apparatus of the present invention, and in the figure, reference numeral 11 indicates a supply means for supplying powdery radioactive waste together with gas into the container body 13. ing. The supply means 11 has a pipe 15, a valve 16 and a pump (not shown). In the container body 13, a rotary filter 1 made of a cylindrical porous body is provided.
9 are arranged. This rotary filter 19 is made of ceramics, Pearlcon (registered trademark of Daicel Chemical Industries).
And the like. A sprocket 21 for rotating the rotary filter 19 is provided above the rotary filter 19, and a chain 23 is attached to the sprocket 21.
And a geared motor 25 that is connected via the. Further, a pipe 27, which is a suction means for sucking the air in the rotary filter 19, is opened at the upper part of the rotary filter 19. On the outer circumference of the rotary filter 19, a separation plate 29 for scraping off radioactive waste adhering to the outer circumference of the rotary filter 19 is arranged at a constant interval, for example, 1 mm, from the rotary filter 19. The lower part of the container body 13 is open to the hopper 31.

In the radioactive waste separation device configured as described above, the granular radioactive waste is placed in the container body 13 after being supplied into the container body 13 through the pipe 15 together with air as a transfer fluid. As shown in FIG. 2, the rotary filter 19 made of a cylindrical porous body is attached to the outer periphery of the rotary filter 19 and is sequentially laminated to form an adhesion layer 33. If the thickness exceeds 1 mm, for example, the rotary filter is formed. It is scraped off by a separating plate 29 which is arranged at a constant interval on the outer circumference of 19. The scraped radioactive waste is transferred from the bottom of the container body 13 to the hopper 31.
Be dropped into.

On the other hand, as shown by the arrow in FIG. 2, the gas that has passed through the rotary filter 19 made of a porous body is discharged to the outside from the pipe 27 sucked by the suction means.

Thus, in the radioactive waste separation device configured as described above, the granular radioactive waste is positively attached to the outer periphery of the rotary filter 19 to form the adsorption layer (precoat) 33 having a constant thickness. Since it is formed, the adsorption layer 33 acts as a separation surface of air and radioactive waste, that is, as a kind of filter, and the separation efficiency can be greatly improved as compared with the conventional radioactive waste separation device.

Further, since the separation efficiency is improved, it is not necessary to filter the air when discharging the air from which the radioactive waste has been separated, unlike the conventional cyclone-type radioactive waste separating device.

Furthermore, since a constant gap is formed between the outer periphery of the rotary filter 19 and the separation plate 29, the tip of the separation plate 29 does not come into contact with the outer periphery of the rotary filter 19, and the life of the rotary filter 19 is improved. It can be extended.

Further, in the radioactive waste separation device configured as described above, as shown in FIG. 3, in the fine pores 35 formed in the porous body of the rotary filter 19, the radioactive waste 37 in the form of powder or granules. Are crosslinked, but when this crosslink is formed, the micropores 3
The inflow of radioactive waste into 5 is blocked, and only air will flow in. Therefore, it is possible to reliably prevent the fine holes 35 from being closed. In addition, when the rotary filter 19 is clogged due to long-term use, by supplying air from the pipe 27 into the rotary filter 19 in reverse,
Backwashing is possible easily.

〔The invention's effect〕

As described above, according to the present invention, since the adsorption layer is formed on the outer periphery of the rotary filter, it is possible to provide the radioactive waste separation device capable of obtaining sufficient separation efficiency of radioactive waste from gas. There is an advantage.

BRIEF DESCRIPTION OF THE DRAWINGS FIG. 1 is a vertical sectional view showing an embodiment of the radioactive waste separating apparatus of the present invention, FIG. 2 is a vertical sectional view showing the vicinity of the rotary filter of FIG. 1, and FIG. FIG. 3 is an explanatory view showing cross-links formed in fine pores of a porous body. 11 ... Supplying means, 13 ... Container body, 19 ... Rotating filter, 29 ... Separating plate.

Claims (2)

[Claims] 1. A supply means for supplying powdery radioactive waste together with gas into a container body, a rotary filter comprising a cylindrical porous body disposed in the container body, and the rotary filter. A suction means for sucking gas that has passed from the outer circumference toward the inner circumference, and a separation plate for scraping off the radioactive waste adhering to the outer circumference of the rotary filter, which is arranged at a constant interval on the outer circumference of the rotary filter. A radioactive waste separation device comprising: 2. The radioactive waste separation device according to claim 1, wherein the gas is air.