JPS58140696A - Radioactive liquid waste processing vessel - Google Patents

Abstract

(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

[Detailed description of the invention] The present invention is an improvement of a radioactive waste liquid treatment device.

In more detail, the impurities are removed from the waste liquid containing radioactive impurities and proboscis, and the impurities are removed from the filament-wrapped layer of the filter element. The present invention relates to a radioactive waste liquid treatment device that is easy to manufacture and handle, and is highly safe, capable of removing the impurities with @ and disposing of the filtration field with a filter element attached thereto.

Conventionally, radioactive waste liquid is treated using a filter as shown in Fig. 1 to remove radioactive impurities.
and a lid 4 having a liquid supply pipe 6 and a liquid discharge pipe 7, and a container a2.
It consists of a discharge valve 8 and the like attached to the bottom of the container, and is handled by being placed in a drum 9 with a shielding member 10 inside. The filter element 3 is connected to the waste liquid treatment line, and when impurities adhere to the filtration layer of the filter element 3 attached to each vessel 2 and the filtration efficiency decreases to a predetermined value, the supply from the waste liquid treatment line is removed. At the same time, the waste liquid in the container 2 is discharged from the discharge valve 8.Then, the filter 1 is removed from the waste liquid treatment line and transported to a dismantling plant.
1. Remove the lid 4 from the container 2, take out the filter element 3 to which radioactive impurities are attached, and remove the shielding member 1.
O is placed in a drum can 9 with an inner bag together with cement slurry, solidified, and stored at a predetermined location.

However, since the filter element with radioactive impurities attached to it is taken out of the filter as mentioned above and placed in a pre-fabricated drum together with cement slurry to solidify, even with protective equipment in place, radioactive impurities are scattered during the operation. There is a possibility of contamination or exposure to radiation in unexpected places. In addition, the work is very dangerous and requires a very long time to perform the VC carefully.
It is necessary to prepare a drum for disposing of the router element, and a frame is required to serve as the core for installing the shielding member into the drum, as well as assembly and removal work of the frame is required. There were some problems.

The present invention was obtained as a result of studies aimed at solving the above-mentioned problems in waste liquid treatment.
The can, the shielding member, and the filter are integrally formed by positioning the can with a spacing holder or the like so as to have a predetermined space on the side and bottom, and injecting the space Kjl shielding member with an fLIIb letter and solidifying it. The present invention provides a radioactive waste liquid treatment device that is easy to handle and highly safe.

A schematic sectional view of one row of the radioactive waste liquid treatment device of the present invention is shown in FIG. 2, and a plan view is shown in FIG. 3, and the configuration will be explained based on the drawings.

It is an 11-case drum, and is a spacing holder for positioning the filter 13 in the 12-case drum 11 so that it has a predetermined space at the side and bottom, and the cement slurry is injected into the space and solidified. This is the body of a 6 tsqp vessel 13 made of concrete for dead bodies, and a cover plate 16 and a bottom plate 17 are fixed to the ends. 18 is a partition plate, which forms a liquid collection chamber between the cover plate 16 and a filter element made of a 19-hole cylinder wrapped with filament such as synthetic fiber; 20 is a filter element that forms a liquid collection chamber between the partition plate 18 and the filter. This is a seal fitting installed between elements 19.

Reference numeral 21 is a seal cap attached to the bottom of the filter element 19, which is pressed by a spring 22, and a waste liquid supply pipe fixed to the cover plate 16 and the partition plate 18. A metal fitting 24 for connection is attached to the inlet end. is the installation. , 25 is a liquid discharge pipe attached to the lid plate 16, and a connecting fitting 26 is attached to the outlet end. This is a residual liquid discharge pipe whose one end is inserted into the body and fixed to the lid plate 16 and the partition plate 1B, and a connecting fitting 28 is attached to the outlet end.

A filter element 19 is attached to the residual liquid discharge pipe 27.

Waste liquid treatment operation using the radioactive waste liquid filter configured as described above (The operation will be explained below) The radioactive waste liquid treatment device is loaded on a forklift and transported to a predetermined location of the waste liquid treatment line (not shown), and the waste liquid of the line is removed. fj for the supply pipe, liquid discharge pipe, and residual liquid discharge pipe! Processing 6
Waste liquid supply pipe 23, liquid discharge pipe 25 and residual liquid discharge pipe 27
The fittings for each joint are connected by a joint that can be attached and detached with one touch, such as those commonly available on the market. When each tube is connected, first, an aqueous solution of a precoating material such as a cation exchange resin is supplied from the II liquid supply pipe 23 to form a layer on the filter element 19 in the filter 13, and is discharged from the liquid discharge pipe 25. When a cation exchange resin layer of a predetermined thickness is deposited on the surface of the filter element 19 and a filtration layer is formed, the liquid supply line is switched and the radioactive waste liquid is supplied. Radioactive impurities are removed from the waste liquid supplied to the 1lliI section 13 by the filtration layer of each filter element 19, and the impurity-free liquid passes through the filament winding section and the perforated cylinder and is passed through the lid plate 16 and the partition plate 18. The liquid collects in the formed liquid collection chamber, and is discharged from the liquid discharge pipe 27 to the waste liquid treatment line (
(not shown). When a predetermined amount of waste liquid is treated and impurities adhere to the filtration layer of the filter element 19 and the filtration efficiency decreases to a predetermined value, the waste liquid supply valve of the waste liquid treatment line is closed, and the liquid discharge valve is also closed. Next, turn the residual liquid discharge valve on the waste liquid treatment line to S! At the same time, the waste liquid supply line and the compressed air supply line are switched to supply compressed air to the waste liquid supply pipe 23.

When compressed air is supplied to the body 13, the waste liquid remaining in the body is pressed from above, and radioactive impurities are removed by a layer of the filter element 19 attached to the residual liquid discharge pipe 27. The remaining liquid is sent to the waste liquid treatment line through the residual liquid discharge pipe i7. When the waste liquid in the barrel is almost gone, close the compressed air supply valve and residual liquid discharge valve of the waste liquid treatment line.

Next, remove the joint of the container of the radioactive waste liquid L8 container and disconnect it from the waste liquid treatment line. The body parts and materials are attached to the separated disposal vessel, 9M29 (dotted line in Figure 2) is attached, and the disposal vessel is lifted onto a forklift and transported to a predetermined location for storage.

The present invention can be carried out as described above, by sequentially using new processing devices and carrying out the above operations to treat radioactive waste liquid, but it is not limited to the embodiments. The can may be a drum as in the embodiment, or may have a curved shape (oil inside, polygon), and may be made of metal as long as it is resistant to breakage and corrosion.

. The shielding member may be made of ordinary concrete, heavy concrete containing pyrite, or lead.

The O spacing holder should be of a shape and number to form a space between the can and the filter and hold the opening filter in place until the shielding member is injected and solidified. It may be attached to the body or inside the can.

The O-filter should preferably have a structure in which all liquid can be supplied and discharged from the upper part, and structure 4, which has a residual liquid discharge pipe, is preferable.

The radioactive waste liquid treatment device of the present invention has the following effects because the can, the shielding member, and the filter are integrally formed as described above.

Since the filter is positioned in the can with a spacer and the shielding member is integrally molded by injection, there is no need for a frame for the core to house the shielding member in the can. This eliminates the need for assembling and disassembling the inside of the can, which can save a large amount of costs and the number of workers.

Since a treatment device that integrates a 0 can, a shielding member, and a Pa device is used, there is no need to remove filter elements with radioactive impurities during waste liquid treatment, and the liquid supply and
The licking work is simple and can be done simply by attaching and detaching the joint of the discharge pipe, and the safety is high.

During transportation of the treatment device used for O waste liquid treatment, the treatment device is integrated as described above, so even if the treatment device is photographed or hit directly during transportation, the filter will not fly out or the shielding member will be damaged. It's safe and there's nothing to do

[Brief explanation of the drawing]

The first figure is a schematic sectional view showing one embodiment of a conventional filter, and the second figure is a schematic cross-sectional view showing one embodiment of the radioactive waste liquid treatment device of the present invention. It is a front view. FIG. 3 is a schematic plan view. 11...Can, 12...Space holder, 13...Filter, 14...Concrete for thicket shielding, 15...Body part,
16... Lid plate, 17... Bottom plate, 18... Partition plate,
19... Filter element, 20... 7-lupatkin, 21... Seal cap, 22... Spring, 23... Waste liquid supply pipe, 25... Liquid discharge pipe, 2
7... Residual liquid discharge pipe. 'l! J/ Figure

Claims (1)

[Claims] 1. Place the filter with the filter element inside the can.
Using a spacer, etc., position the sides and bottom so that there is a predetermined space, and then set Zg! A radioactive waste liquid treatment device characterized in that a can, a shielding member, and a filter 4 are integrally formed by injecting a shielding member in a fluid state between them and solidifying it.