JP6046574B2 - Method for treating radioactive liquid waste and apparatus for treating radioactive liquid waste - Google Patents

Description

  The present invention relates to a radioactive waste liquid treatment method and a radioactive waste liquid treatment apparatus, and more particularly to a radioactive waste liquid treatment method and a radioactive waste liquid treatment apparatus suitable for removing radionuclides contained in a radioactive waste liquid containing particulate components such as soil. About.

  One of the methods for treating radioactive liquid waste containing radioactive nuclides generated in nuclear facilities, for example, nuclear power plants, is a method of adsorbing and removing ionic radioactive nuclides with an inorganic adsorbent and ion exchange resin. .

  An example of a treatment method for adsorbing and removing a radionuclide from a radioactive liquid waste is described in, for example, Ikeda et al., Proceedings of GLOBAL 2011, Dec.11-16, 2011, Makuhari, Japan, USA, Paper No. 524705 (2011). Has been. In this radionuclide adsorption / removal treatment method, radioactive waste liquid is passed through a container filled with an adsorbent, and ionic radionuclides contained in the radioactive waste liquid are adsorbed on the adsorbent and removed. In addition, before supplying a radioactive waste liquid in the container filled with the adsorbent, the particulate matter contained in the radioactive waste liquid is removed by a filtration device.

  For example, JP2013-57599A describes a method for treating radioactive sewage. Iron ferrocyanide is added into the container into which the radioactive liquid waste flows, and the radioactive cesium contained in the radioactive liquid waste is adsorbed on the iron ferrocyanide, and then a zeolite adsorbent is added to the radioactive liquid waste in the container. Radioactive strontium contained in the radioactive liquid waste is adsorbed on the zeolite adsorbent. Furthermore, an inorganic flocculant is added to the radioactive liquid waste. By the action of the inorganic flocculant, an aggregate of solid particles including iron ferrocyanide particles adsorbed with radioactive cesium and zeolite adsorbent particles adsorbed with radioactive strontium is formed, and this aggregate is settled and separated. The

  Furthermore, in the radioactive waste liquid processing method described in JP-A-2002-31697, a filtration device and an ion exchange device are used. An ultrafiltration membrane is used as a filtration device. The colloidal component contained in the radioactive liquid waste is removed by the ultrafiltration membrane, and then the ionic radionuclide contained in the radioactive liquid waste is removed by the ion exchange device. In the radioactive waste liquid treatment method described in JP 2013-108808 A, the colloidal component contained in the radioactive waste liquid is removed by a filtration device (for example, an ultrafiltration membrane). The radioactive waste liquid is supplied to the filtration device after sodium hydroxide is added to the radioactive waste liquid and the pH of the radioactive waste liquid is adjusted to a predetermined value. The radioactive waste liquid from which the colloid has been removed by the filtration device is supplied to an adsorption tower packed with a titanate adsorbent. Since the titanate adsorbent easily adsorbs strontium, strontium contained in the radioactive waste liquid is removed in the adsorption tower.

JP2013-57599A JP 2002-31697 A JP 2013-108808 A

Ikeda et al., Proceedings of GLOBAL 2011, Dec.11-16, 2011, Makuhari, Japan, USA, Paper No. 524705 (2011)

  When discharging treated water from which radioactive nuclides have been removed from radioactive liquid waste, the concentration of the radioactive nuclides in the treated water is required to be below the reference value. An example of the reference value is that the measurement result of the concentration of the radionuclide by the radiation measuring instrument of the specified specification is not more than the measurement lower limit value of the radiation measuring instrument.

  Radioactive liquid waste containing radionuclides, particularly contaminated water generated in nuclear facilities, may contain particulate matter such as soil, sand components, concrete fragments and plants. In many cases, this radioactive waste liquid is once stored in a tank or the like, and a substance having a large particle size contained in the radioactive waste liquid is settled and removed in the tank. Thereafter, the radionuclide contained in the radioactive liquid waste from which the substance having a large particle size has been removed is removed by an adsorbent through a filtration operation or precipitated by adding a coagulating precipitant to the radioactive liquid waste.

  The inventors investigated the distribution of cesium-137 using a soil sample to which cesium-137, which is a radionuclide, was attached. First, the soil sample was suspended in water, and the water containing the soil sample was allowed to stand for a while to separate into a sediment component and a supernatant water. Thereafter, the supernatant water was filtered with filter paper having different openings, and the concentrations of 1 micrometer or more particles, 1 micrometer or less microparticles (colloid), and cesium-137 in the ionic component in the finished water were measured. . As a result, it was found that cesium-137 contained particles of 1 μm or more in 98.5%, fine particles and colloids of less than 1 μm in 1%, and 0.5% in the solution. From this, in order to remove the radionuclide until it becomes below the measurement lower limit value of the radiation measuring instrument, in addition to the particle component that can be removed by physical filtration and the ion component that is removed by chemical adsorption with the adsorbent, fine particles and It was found that the colloids also needed to be removed.

  In the method described in Ikeda et al., Proceedings of GLOBAL 2011, Dec.11-16, 2011, Makuhari, Japan, USA, Paper No. 524705 (2011) In the adsorption separation of the ionic component, the fine particles and the colloid component cannot be removed by the filtration device and the adsorbent, and it is difficult to make the radioactive concentration of the treated water below the lower limit of measurement.

  On the other hand, in the method for treating radioactive sewage described in JP2013-57599A, when a precipitate is formed by adding a coagulating precipitant to radioactive sewage, along with an adsorbent that adsorbs particles and ionic components, When fine particles and colloids are contained in radioactive sewage, the fine particles and colloids also aggregate and precipitate, so that it is possible to make the radioactive concentration of treated water below the lower limit of measurement. However, there is a problem that the amount of the precipitate containing radioactive material generated by adding the coagulating precipitant is large, and the method for storing and disposing of the precipitate containing moisture is difficult.

  In the methods for removing radionuclides described in JP-A-2002-31697 and JP-A-2013-108808, particle components, fine particles, and colloidal components can be removed by an installed ultrafiltration device. The outer filtration membrane has a small pore size, and when removing a large amount of particle components, the ultrafiltration membrane may be clogged.

JP-A-has been method for treating a radioactive liquid waste according to 2002-31697 Patent Gazette is provided with the clogging prevention device ultrafiltration membrane. The clogging prevention device has a physical mechanism for the ultrafiltration membrane, such as a vibration mechanism that vibrates the ultrafiltration membrane and a rotation mechanism that rotates the ultrafiltration membrane. By applying a physical impact to the ultrafiltration membrane from the clogging prevention device, the particle components deposited on the ultrafiltration membrane are separated from the ultrafiltration membrane and discharged as a slurry. Storing and storing the slurry having a high water content has a problem in terms of the amount of radioactive waste generated and property stability. In the radioactive waste liquid processing method described in JP2013-108808A, pH adjustment is necessary, and a reagent for pH adjustment, a stirring device, and an analyzer for pH confirmation are required.

  The objective of this invention is providing the processing method of the radioactive waste liquid which can remove a radioactive substance from a radioactive waste liquid to below a measurement lower limit with a simple apparatus structure, reducing the generation amount of a radioactive waste.

A feature of the present invention that achieves the above-described object is that a colloidal substance, a particulate matter having a particle size larger than that of the colloidal substance, and a radioactive waste liquid containing the radioactive substance are supplied to the filtration device to remove the particulate matter by the filtration device The colloidal substances contained in the radioactive liquid waste that has been removed and discharged from the filtration device are removed with an electrostatic filter. apparatus is in the child removed by.

  Particulate matter with a particle size larger than that of colloidal material is removed with a filtration device, colloidal material is removed with an electrostatic filter, and radioactive material is removed with an adsorption device. The amount of generation can be reduced, and radioactive substances can be removed up to the lower limit of measurement.

  ADVANTAGE OF THE INVENTION According to this invention, it can remove a radioactive substance from a radioactive waste liquid to below a measurement lower limit with a simple apparatus structure, reducing the generation amount of a radioactive waste.

BRIEF DESCRIPTION OF THE DRAWINGS It is a block diagram of the radioactive waste liquid processing apparatus used for the processing method of the radioactive waste liquid of Example 1 which is one suitable Example of this invention. It is explanatory drawing which shows the amount of radioactive waste generated with the processing method of the radioactive waste liquid of Example 1. FIG. It is a block diagram of the radioactive waste liquid processing apparatus used for the processing method of the radioactive waste liquid of Example 2 which is another suitable Example of this invention. It is a block diagram of the radioactive waste liquid processing apparatus used for the processing method of the radioactive waste liquid of Example 3 which is another suitable Example of this invention.

Examples of the present invention will be described below.

  A method for treating radioactive liquid waste according to embodiment 1 which is a preferred embodiment of the present invention will be described with reference to FIG. Furthermore, the radioactive waste liquid processing apparatus used for the processing method of this radioactive waste liquid is demonstrated using FIG.

  The radioactive liquid waste treatment apparatus 1 used in this embodiment includes a filtration device 2, a colloid removal device 3, and an adsorption device 5. The filtration device 2 is a device for physically filtering the particle components contained in the radioactive waste liquid, and has a cartridge filter (or pleat filter) filled with a filter material inside. The filtration device 2 removes particles of about 1 μm or more contained in the radioactive liquid waste. The colloid removing device 3 has a plurality of electrostatic filters 4 installed in the casing. The adsorption device 5 has a plurality of adsorption towers 6. Adsorbents selected according to the type of radionuclide contained in the radioactive liquid waste are packed in each adsorption tower 6 separately. A radioactive waste liquid supply pipe 7 is connected to the filtration device 2. The filtration device 2 and the colloid removal device 3 are connected by a connection pipe 8. Among the plurality of adsorption towers 6 in the adsorption apparatus 5, the adsorption tower 6 located on the most upstream side is connected to the colloid removing apparatus 3 by a connection pipe 9. Each adsorption tower 6 in the adsorption device 5 is sequentially connected by a pipe 10. The discharge pipe 11 is connected to the adsorption tower 6 located on the most downstream side among the plurality of adsorption towers 6 in the adsorption device 5.

  As an adsorbent to be packed in each adsorption tower 6 of the adsorption device 5, for example, natural zeolite, artificial zeolite and silicotitanate are selectively used to selectively adsorb radioactive cesium and radioactive strontium. In order to adsorb, for example, a hydrous cerium-containing adsorbent is used, and in order to selectively adsorb radioactive heavy metals, for example, oxine-impregnated activated carbon is used. These adsorbents are packed in each adsorption tower 6 separately. As the adsorbent for adsorbing the radionuclide used in the adsorption device 5, at least one of zeolite, ferrocyanide, titanate compound, titanate compound, ion exchange resin, chelate resin, activated carbon and impregnated activated carbon is used.

  The processing method of the radioactive waste liquid of a present Example using the radioactive waste liquid processing apparatus 1 is demonstrated. In the method for treating the radioactive liquid waste of the present embodiment, the radioactive liquid waste generated in the boiling water nuclear power plant is processed. Radioactive waste liquid containing particles of 1 μm or more, a negatively charged colloid, and two or more types of radionuclides drive a radioactive waste liquid supply pipe 7 by driving a pump (not shown) provided in the radioactive waste liquid supply pipe 7. Is supplied to the filtration device 2. Particles of 1 μm or more contained in the radioactive liquid waste are removed by the cartridge filter in the filtration device 2. The radioactive waste liquid discharged from the filtration device 2 is supplied to the colloid removal device 3 through the connection pipe 8.

  The colloid contained in the radioactive liquid waste is removed by the electrostatic filter 4 in the colloid removing device 3. Fine particles of less than 1 μm are called colloids. The surface of the colloid is positively or negatively charged. Whether the colloid is positively or negatively charged depends on the material forming the colloid and the surface structure. In general, colloids derived from soil components are often negatively charged. In this embodiment, since the electrostatic filter 4 in the colloid removing device 3 is positively charged when energized, the negatively charged colloid derived from the soil component contained in the radioactive waste liquid is included in each electrostatic filter. 4 is attached to the surface and removed. It is not necessary to adjust the pH of the radioactive liquid waste supplied to the colloid removing device 3. In the electrostatic filter 4, colloidal particles having a particle size in the range of about 1 nm or more and less than 1 μm are removed.

  The radioactive liquid waste from which the colloidal particles have been removed is supplied to the adsorption tower 6 of the adsorption device 5 through the connection pipe 9. The radioactive liquid waste supplied to the adsorption device 5 does not contain particle components and colloids. For example, radioactive nuclides such as radioactive cesium, radioactive strontium and radioactive antimony contained in the radioactive liquid waste are ions. Each time the radioactive liquid waste passes through the plurality of adsorption towers 6, each radionuclide such as radioactive cesium, radioactive strontium, and radioactive iodine contained in the radioactive liquid waste is separately adsorbed by the adsorbent 6 and removed. Each adsorption tower 6 is filled with a corresponding adsorbent in an amount capable of sufficiently adsorbing the entire amount of each radionuclide contained in the radioactive liquid waste. For this reason, the density | concentration of each radionuclide contained in the treated water discharged | emitted from the adsorption apparatus 5 to the discharge pipe 11 becomes below a measurement lower limit. The treated water discharged from the adsorption device 5 is supplied to and stored in a storage tank (not shown) through the discharge pipe 11. When the concentration of each radionuclide contained in the treated water flowing in the discharge pipe 11 was measured with a radiation measuring instrument (not shown) provided in the discharge pipe 11, the concentration of each radionuclide was less than the measurement lower limit value. .

  Each adsorbent packed in each adsorption tower 6 of the adsorption device 5 has sufficient adsorption performance without adjusting the pH of the treated water, and the pH of the treated water discharged from the adsorption device 5 is also neutral (pH = 6). Since it is in the range of ~ 8), it is not necessary to adjust the pH after the treatment.

  In order to verify the effect of the radioactive waste liquid treatment method of this example, the amount of radioactive waste generated by the radioactive waste liquid treatment method of this example was evaluated. The amount of radioactive waste generated by the method for treating radioactive waste liquid of this example is shown in FIG. For comparison, the amount of waste generated in the known method of treating radioactive waste liquid by adding a coagulating precipitant was also evaluated, and is shown in FIG. In the known example, the total amount of radioactive waste generated in each of the filtration step, the adsorption step with the adsorbent, and the coagulation sedimentation step (sludge generation) with the addition of the coagulation precipitant increases. On the other hand, in this embodiment, the total amount of the filter medium 2 (cartridge filter, etc.), the waste filter of the electrostatic filter 4 and the waste adsorbent of the adsorption device 5 that becomes radioactive waste is a coagulant precipitant. The amount of radioactive waste generated was reduced to 1/3 or less of the total amount of radioactive waste generated by the known radioactive waste processing method by addition.

  According to the present embodiment, the amount of radioactive waste generated can be reduced with a simple device configuration including the filtration device 2, the colloid removal device 3 using the electrostatic filter 4, and the adsorption device 5. It can be removed up to the lower limit of measurement. The radioactive waste generated by the processing method of the radioactive waste liquid of this embodiment is the filter medium of the filtration device 2, the waste filter of the electrostatic filter, and the waste adsorbent of the adsorption device 5, and no precipitation occurs, and the radioactive waste Can be reduced.

  When the radioactive liquid waste contains a positively charged colloid as a colloid, a colloid removing device having a negatively charged electrostatic filter may be used instead of the colloid removing device 3.

  A method for treating radioactive waste liquid according to embodiment 2, which is another preferred embodiment of the present invention, will be described with reference to FIG. Furthermore, the radioactive waste liquid processing apparatus used for the processing method of this radioactive waste liquid is demonstrated using FIG.

  The radioactive liquid waste processing apparatus 1A used in the present embodiment has a configuration in which a colloid removing apparatus 3A is added to the radioactive liquid waste processing apparatus 1. The colloid removing device 3A has a plurality of electrostatic filters 4A installed in the casing. The colloid removing device 3A is connected to the colloid removing device 3 by a connection pipe 8A, and further connected to an adsorption tower 6 located at the most upstream side in the adsorption device 5 by a connection pipe 9. Unlike the electrostatic filter 4 of the colloid removing device 3, each electrostatic filter 4A of the colloid removing device 3A is negatively charged by energization. The other configuration of the radioactive liquid waste treatment apparatus 1A is the same as that of the radioactive liquid waste treatment apparatus 1. The electrostatic filter 4 of the colloid removing device 3 is positively charged.

  The method for treating the radioactive waste liquid according to the present embodiment, which is performed using the radioactive waste liquid treatment apparatus 1A, will be specifically described. In the method for treating the radioactive liquid waste of the present embodiment, the radioactive liquid waste generated in the boiling water nuclear power plant is processed. Differences from the first embodiment will be mainly described.

  Radioactive liquid containing 1 μm or more particles, negatively charged colloid, positively charged colloid and two or more types of radionuclides, and two or more types of radionuclides 7 is supplied to the filtration device 2, and is further supplied to the colloid removing device 3 through the connection pipe 8. Particles of 1 μm or more and negatively charged colloid are removed by the filtration device 2 and the colloid removal device 3. The radioactive liquid waste discharged from the colloid removing device 3 is supplied to the colloid removing device 3A through the connection pipe 8A. Each electrostatic filter 4A of the colloid removing device 3A is negatively charged. For this reason, the positively charged colloid contained in the radioactive liquid waste adheres to each negatively charged electrostatic filter 4A and is removed from the radioactive liquid waste. The radioactive liquid waste discharged from the colloid removing device 3A is supplied to each adsorption tower 6 of the adsorption device 5, and each radionuclide contained in the radioactive liquid waste is removed as in the first embodiment.

  In the present embodiment, each effect produced in the first embodiment can be obtained. Further, in this embodiment, since the colloid removing device 3 using the colloid removing device 3 provided with the positively charged electrostatic filter 4 and the colloid removing device 3A provided with the negatively charged electrostatic filter 4A are used as the colloid removing device. The negatively charged colloid and the positively charged colloid contained in the waste liquid can be removed, and the load on the adsorption device 5 in the subsequent stage can be reduced.

  A method for treating radioactive waste liquid according to embodiment 3, which is another preferred embodiment of the present invention, will be described with reference to FIG. Furthermore, the radioactive waste liquid processing apparatus used for the processing method of this radioactive waste liquid is demonstrated using FIG.

  The radioactive liquid waste treatment apparatus 1B has a configuration in which a radiation detector 12 and a bypass pipe 15 are added to the radioactive liquid waste treatment apparatus 1. The on-off valve 14 is provided in the connection pipe 9, and the radiation detector 12 is disposed on the connection pipe 9 side upstream of the on-off valve 14. One end of the bypass pipe 15 provided with the on-off valve 16 is connected to the connection pipe 9 between the colloid removing device 3 and the on-off valve 14. The other end of the bypass pipe 15 is connected to the discharge pipe 11. Other configurations of the radioactive liquid waste treatment apparatus 1B are the same as those of the radioactive liquid waste treatment apparatus 1.

  The processing method of the radioactive waste liquid of the present Example implemented using the radioactive waste liquid processing apparatus 1B will be specifically described. In the method for treating the radioactive liquid waste of the present embodiment, the radioactive liquid waste generated in the boiling water nuclear power plant is processed. Differences from the first embodiment will be mainly described.

  A radioactive waste liquid containing particles of 1 μm or more, a negatively charged colloid, and two or more types of radionuclides is supplied to the filtration device 2 through the radioactive waste liquid supply pipe 7 and further supplied to the colloid removal device 3. Particles of 1 μm or more contained in the radioactive liquid waste are removed by the filtering device 2, and the negatively charged colloid is removed by the electrostatic filter 4 of the colloid removing device 3.

  The radiation detector 12 measures the radioactivity concentration of the radioactive liquid waste discharged from the colloid removing device 3 and flowing in the connection pipe 9. When the radioactivity concentration measured by the radiation detector 12 is larger than the measurement lower limit value of the radiation detector 12, the on-off valve 14 is opened and the on-off valve 16 is closed, and the radioactive waste liquid discharged from the colloid removing device 3 is adsorbed. Each adsorption tower 6 of the adsorption device 5 supplied to the apparatus 5 adsorbs and removes each ionic radionuclide contained in the radioactive waste liquid separately. The radioactivity concentration of the treated water discharged from the adsorption device 5 to the discharge pipe 11 after each radionuclide is removed by the adsorption device 5 is reduced below the measurement lower limit value of the radiation detector 12.

  When the radioactive concentration of the radioactive waste liquid flowing through the connection pipe 9 measured by the radiation detector 12 is equal to or lower than the measurement lower limit value of the radiation detector 12, the on-off valve 16 is opened and the on-off valve 14 is closed. The radioactive waste liquid flowing in the connection pipe 9 is guided to the discharge pipe 11 through the bypass pipe 15. At this time, radioactive waste liquid flowing in the connection pipe 9 and having a measurement lower limit value or less is not supplied to the adsorption device 5.

  The on-off valves 14 and 16 are opened or closed manually or automatically based on the radioactivity concentration measured by the radiation detector 12. When the on-off valves 14 and 16 are manually opened and closed, the radioactivity concentration measured by the radiation detector 12 is displayed on a display device (not shown), and the on-off valves 14 and 16 are viewed by an operator who sees the displayed radioactivity concentration. Is opened and closed. In order to automatically open and close the on-off valves 14 and 16, a control device (not shown) that inputs the radioactivity concentration measured by the radiation detector 12 opens and closes the on-off valves 14 and 16.

  The radiation detector 12 measures radiation (for example, alpha rays, beta rays, gamma rays, and X-rays) emitted by radionuclides contained in the radioactive liquid waste, and is, for example, an ionization chamber, a scintillation type detector, or a semiconductor type detector. is there. The radioactivity measured by the radiation detector 12 may be one type or two or more types.

  In the present embodiment, each effect produced in the first embodiment can be obtained. Further, when the treated water does not contain ionic radioactive substances, the treated water is not supplied to the adsorption device 5, so treated water by elution of radionuclides from the adsorbent in each adsorption tower 6 when the treated water passes through the adsorption device 5. Re-contamination can be avoided, and the performance deterioration of the adsorbent due to avoiding unnecessary water flow can be reduced.

  In the radioactive liquid waste treatment apparatus 1B, the colloid removal apparatus 2 is connected to the colloid removal apparatus 2 by the connection pipe 8A via the connection pipe 8A, and the colloid removal apparatus 2A is provided with the connection pipe 9 in the same manner as the radioactive liquid waste treatment apparatus 1A. Also good. In this case, the radiation detector 12 measures the radioactivity concentration of the radioactive liquid waste discharged from the colloid removing device 2A. When the measured radioactivity concentration is below the measurement lower limit value of the radiation detector 12, the on-off valve 16 is opened and the on-off valve 14 is closed. When the measured radioactivity concentration is larger than the measurement lower limit value, the on-off valve 14 is opened and the on-off valve 16 is closed.

  The processing method of each radioactive waste liquid of Examples 1-4 is applicable also to the processing of the radioactive waste liquid generated in the pressurized water nuclear power plant.

  DESCRIPTION OF SYMBOLS 1,1A, 1B ... Radioactive waste liquid processing apparatus, 2 ... Filtration apparatus, 3 and 3A ... Colloid removal apparatus, 4 and 4A ... Electrostatic filter, 5 ... Adsorption apparatus, 6 ... Adsorption tower, 12 ... Radiation detector, 14, 16: Open / close valve, 15: Bypass piping.

Claims (8)

  A colloidal material, a radioactive waste liquid containing a particulate material having a particle size larger than that of the colloidal material and a radioactive material is supplied to a filtration device, the particulate material is removed by the filtration device, and discharged from the filtration device. The colloidal substance contained in the radioactive waste liquid is removed by an electrostatic filter, the radioactive waste liquid from which the colloidal substance has been removed is supplied to an adsorption device, and the radioactive substance contained in the radioactive waste liquid is removed by the adsorption device. A method for treating a radioactive liquid waste comprising removing the radioactive liquid waste.   The method for treating a radioactive liquid waste according to claim 1, wherein the removal of the negatively charged colloidal substance is performed using the electrostatic filter that is positively charged.   The method for treating a radioactive liquid waste according to claim 1 or 2, wherein the removal of the positively charged colloidal substance is performed using the electrostatic filter that is negatively charged.   The radioactivity concentration of the radioactive liquid waste from which the colloidal material has been removed is measured, and when the measured radioactivity concentration is greater than the measurement lower limit value of the radioactivity concentration, the colloidal material has been removed. The radioactive waste liquid is supplied to the adsorption device, and when the measured radioactivity concentration is equal to or lower than the measurement lower limit value, the radioactive waste liquid from which the colloidal material has been removed is bypassed the adsorption device. A method for treating radioactive liquid waste according to 1. Colloidal material, a filtration device for removing front Symbol grain child matter from the radioactive liquid waste containing particulate materials and radioactive materials larger particle size than the colloidal material, is connected to the filtration apparatus, the colloidal material colloidal removal device having an electrostatic filter for removing, connected to said colloid removal apparatus, radioactive waste treatment apparatus characterized by comprising a suction device having an adsorbent to adsorb the radioactive material.   The colloid removal device has a first colloid removal device having a positively charged first electrostatic filter that removes the negatively charged colloidal material, and removes the positively charged colloidal material. The radioactive waste liquid processing apparatus according to claim 5, further comprising a second colloid removing apparatus having a second electrostatic filter that is negatively charged.   A connection pipe connecting the colloid removal apparatus and the adsorption apparatus; a first on-off valve provided in the connection pipe; and the connection pipe connected between the colloid removal apparatus and the first on-off valve; A bypass pipe for bypassing the device, a second on-off valve provided in the bypass pipe, and a radiation detector for measuring a radioactivity concentration of the radioactive liquid waste flowing in the connection pipe upstream of the first on-off valve; The radioactive waste liquid processing apparatus of Claim 5 provided with these. The adsorbent for adsorbing the radioactive material in the adsorption device, zeolites, ferrocyanide, titanate compounds, ion exchange resins, chelate resins, to claim 5 is at least one of activated carbon and impregnated activated carbon The radioactive waste liquid processing apparatus as described.

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