JP2009244089A - Removing method and removing device of radioactive material and toc - Google Patents

Abstract

<P>PROBLEM TO BE SOLVED: To provide a removing method and a removing device of radioactive material and TOC (total organic carbon) , capable of efficiently providing a distillate reusable or releasable in and from a general or existing facility from a radioactive waste liquid, while reducing radioactive waste. <P>SOLUTION: The radioactive waste liquid containing an organic carbon material is fractionated into a residue and a distillate by distillation, under a reduced pressure, and a radioactive material is added to the residue, together with the organic carbon material, thereby the distillate in which the radioactive material is removed and the organic carbon material is reduced is generated. <P>COPYRIGHT: (C)2010,JPO&INPIT

Description

  TECHNICAL FIELD The present invention relates to a method and apparatus for removing radioactive substances and TOC (total organic carbon), and more particularly, to a method and apparatus for removing radioactive substances and TOC from a radioactive waste liquid obtained by decontaminating radioactive contaminants with a decontamination liquid. The present invention relates to a method and apparatus for removing radioactive substances and TOC from radioactive waste liquid obtained by decontaminating radioactive contamination tools and the like used in radiation control areas such as nuclear facilities with a decontamination liquid.

  Nuclear power facilities generate low-level radioactive liquid waste, such as waste liquids for cleaning tools and pipes used in the radiation control area. The radioactive liquid waste must be stored in the power plant premises or stored for a long period of time if the radioactivity level does not decrease to the specified standard, and should be processed in a normal water treatment facility. It is a rule that can not be. In recent years, it has been required not only to remove radioactive substances, but also to reduce the TOC in the waste liquid to a standard defined by laws and regulations.

  Regarding the removal of radioactive substances, Patent Document 1 discloses a method of concentrating radioactive waste liquid with a distiller, sending the distillate to a desalting tower, purifying it, and releasing it from the system, while solidifying the concentrated liquid. ing.

  Regarding removal of TOC, Patent Document 2 discloses a catalyst obtained by wet decomposition of radioactive organic waste by the action of hydrogen peroxide on radioactive organic waste made of filter sludge or ion exchange resin membrane generated from a nuclear power plant. A method is disclosed in which it is treated with a combustion device and separated into condensed water containing no TOC and harmless and odorless exhaust gas.

  Regarding the removal of radioactive substances and COD, Patent Document 3 describes that after radioactive wastewater is oxidized and insolubilized, it is separated into solid and liquid by filtration, gravity sedimentation, coagulation sedimentation, centrifugal separation or flotation separation. A method of removing is disclosed.

JP-A-3-13897 JP 2000-65986 A JP 2002-228895 A

  The above-mentioned Patent Document 1 does not describe TOC. On the other hand, there is no description regarding the removal of radioactive substances in Patent Document 2, and in addition, the processing object of the invention according to the same document is a radioactive organic waste made of filter sludge or an ion exchange resin membrane, and the radioactive waste liquid is not.

  Patent Document 3 describes a method of removing radioactive substances and COD-causing substances by filtration, gravity sedimentation, etc., but in such a solid-liquid separation means, a waste liquid having a TOC concentration of the order of 10,000 ppm is described. It is also difficult to obtain purified water having a TOC concentration of the order of 10 ppm. In addition, when a filtration filter is immediately used to remove radioactive substances, the filtration filter is radioactively contaminated, and on the contrary, there is a problem that radioactive waste increases.

  An object of the present invention is to make it possible to efficiently obtain a distillate that can be reused or discharged in a normal or existing facility from a radioactive liquid waste, and to reduce the volume of the radioactive waste and the TOC. It is providing the removal method and removal apparatus of this.

  In the first aspect of the present invention, the radioactive waste liquid containing an organic carbon substance is distilled under reduced pressure, fractionated into a residue and a distillate, and the residue contains the radioactive substance together with the organic carbon substance. Provided is a method for removing radioactive material and TOC, wherein the radioactive material is removed and the distillate with reduced organic carbon material is produced.

  In a second aspect, the present invention is an apparatus for removing radioactive substances and TOC from a radioactive liquid waste containing an organic carbon substance, wherein the radioactive liquid waste is distilled under reduced pressure, and fractionated into a residue and a distilled liquid. A kettle, heating means for heating the inside of the vacuum distillation kettle to a predetermined temperature, pressure reducing means for depressurizing the inside of the vacuum distillation kettle to a predetermined pressure, and the radioactive carbon together with the organic carbon substance from the vacuum distillation kettle A radioactive substance comprising: a residue collecting means for collecting a residue; and a distillate collecting means for collecting the distillate discharged from the vacuum distillation kettle after the radioactive substance is removed and the organic carbon substance is reduced. And a TOC removal apparatus.

  Generally, under conditions where distillation occurs, if one of temperature and pressure is determined, the other is determined. That is, in the present invention, in order to generate the vacuum distillation, the pressure and the temperature may be set corresponding to each other based on the vapor pressure curve determined by the type of the radioactive liquid waste. Basically, in vacuum distillation, when the pressure is set relatively high, the temperature is set at a relatively high temperature, and when the pressure is set relatively low, the temperature may be set at a relatively low temperature. However, in the vacuum distillation of the present invention, it is preferable to set the pressure and temperature in consideration of, for example, the vacuum distillation treatment time so that the vacuum distillation is industrially effective. Furthermore, it is preferable to determine the pressure and temperature in vacuum distillation in consideration of prevention of mixing of radioactive substances into the distillate side, pressure resistance of the vacuum distillation kettle and pumping capacity for reducing the pressure. Moreover, it is preferable to determine distillation conditions based on the viewpoint that accidents such as fire are highly prevented when the temperature is set low, and the processing time is shortened when the temperature is high.

(1) Since the waste liquid can be fractionated into a residue and a distillate by low-temperature treatment by vacuum distillation of the radioactive waste liquid, scattering of radioactive substances is prevented.
(2) Since the radioactive substance and the organic carbon substance are contained in the residue in a state of being bonded to each other, efficient removal of both is achieved and the cleanliness on the distillate side is improved.
(3) When the radioactive liquid waste is directly applied to a filtration means, for example, a filtration filter, the filtration filter is greatly contaminated with radioactive substances, and this filtration filter becomes radioactive waste. On the contrary, the radioactive waste increases. There is a problem. However, according to the present invention, since radioactive waste liquid is first distilled under reduced pressure to remove radioactive substances, occurrence of such a problem is prevented.
(4) Since a distillate having a TOC concentration of 10 ppm or less, preferably 5 ppm or less can be obtained by vacuum distillation of the radioactive liquid waste, an ultrapure solution having a TOC concentration of 1 ppm or less, such as a detection limit value or less, such as It is easy to obtain ultrapure water. As a result, it can be released into public waters such as lakes, rivers, and seas throughout the country. According to the water quality standard based on the Water Supply Law (Ministry of Health, Labor and Welfare No. 101 of 2003) and Base 46, organic matter (TOC) is defined as 5 mg / l (5 ppm) or less.
(5) Since the liquid is removed from the residue containing radioactive material, the volume of radioactive waste is reduced. On the other hand, the distillate can be reused or processed at the on-site water treatment facility such as a nuclear facility or easily. The TOC and radioactive material are removed to a reasonable level. Moreover, the obtained distillate can be reused as a diluent for a cleaning solution for radioactive contaminants.

  In a preferred embodiment of the present invention, when the radioactive liquid waste is aqueous and the resulting distillate is distilled water, the vacuum distillation temperature is 20 to 85 ° C, preferably 30 to 80 ° C, more preferably 40 to 40 ° C. The pressure is set in the range of 60 ° C., and the pressure at this time is basically determined according to the temperature range with reference to the vapor pressure curve of water. For example, the pressure of vacuum distillation is basically set to 0.0023 to 0.057 MPa, preferably 0.0041 to 0.047 MPa, and more preferably 0.0072 to 0.02 MPa.

  In a preferred embodiment of the present invention, the radioactive liquid waste is an aqueous or organic solvent system. For example, trichloroethylene or perchloroethylene is exemplified as the organic solvent. The temperature and pressure of the vacuum distillation may be basically determined based on the vapor pressure curve of the organic solvent.

  The radioactive waste liquid treated according to the present invention is, for example, a waste liquid after decontaminating radioactive contaminants with an aqueous or organic solvent-based decontamination liquid.

In a preferred embodiment of the present invention, the TOC concentration of the distillate is at least 10 ppm or less, preferably 5 ppm or less. More preferably, it is easy to filter the distillate so that the TOC concentration of the distillate is 1 ppm or less.
In a preferred embodiment of the present invention, the distillate from which the radioactive substance has been removed is generated. In addition, the radioactive substance concentration in the distillate from which the radioactive substance has been removed is less than the detection limit value by the 3σ method.

  In a preferred embodiment of the present invention, the organic carbon contained in the residue is an organic carbon substance attached to a radioactive pollutant, an organic carbon substance contained in a decontamination liquid from which the radioactive pollutant has been decontaminated, and / or Or the organic carbon substance contained in the additive added before the said vacuum distillation originates. For example, the organic carbon contained in the residue is derived from organic substances contained in scales and rust attached to radioactive contaminants, organic acids contained in decontamination liquid, or additives such as oil cleaning agents. This organic carbon (TOC) and radioactive material are present in the residue by chemical or physical adsorption.

  In the removal method according to a preferred embodiment of the present invention, before the vacuum distillation, a neutralizing agent is added according to the pH of the radioactive liquid waste, and the residue contains the components of the neutralizing agent. As a result, the obtained distillate is neutralized and can be easily treated or discharged. Moreover, in the obtained residue, a radioactive substance exists in the organic carbon substance in the neutralizing agent by chemical or physical adsorption. Moreover, the removal apparatus which concerns on preferable embodiment of this invention has the neutralization means which performs the said neutralization process, for example, a neutralization tank.

  For example, when the radioactive liquid waste is acidic, calcium hydroxide may be added as the neutralizing agent, and when it is alkaline, an acid may be added.

  In a preferred embodiment of the present invention, the atmosphere or treatment time of vacuum distillation is adjusted so that the distillation liquid is 95% or more and the residue is 5% or less with respect to 100% of the radioactive waste liquid.

  In a preferred embodiment of the present invention, the temperature and pressure of vacuum distillation and the distillation time are set so that the liquid content of the residue, for example, the water content is 30% or less, more preferably 10% or less. In addition, if the distillation time is lengthened, the liquid content of the residue can be reduced.

  In the removal method according to a preferred embodiment of the present invention, the distillate is filtered. This further removes organic carbon material from the distillate, further reducing the TOC concentration. In the removal apparatus according to a preferred embodiment of the present invention, for example, a carbon filter and an ion exchange resin are arranged in a single stage or multiple stages as filtration processing means.

  In the removal apparatus according to a preferred embodiment of the present invention, a heater or steam as a heating means or a heat source of a vacuum distillation kettle, a pump or an ejector as a pressure reducing means of the vacuum distillation kettle, a distillate tank, a residue recovery means as a distillate recovery means As a residue container, respectively.

  In a preferred embodiment of the present invention, when the radioactive waste liquid is a waste liquid obtained by decontaminating radioactive contaminants with an aqueous decontamination liquid, the decontamination liquid has a total amount of organic acid of 0.4 to 50%. More preferably, it contains 0.4 to 30%, more preferably 0.4 to 20%, more preferably 0.4 to 10%, alternatively 1 to 20%, and more preferably 1 to 10%.

  Preferably, the decontamination solution contains one or more of malic acid, citric acid, formic acid, oxalic acid, glyceric acid, tartaric acid and glycolic acid as the organic acid. Such organic acids are easy to handle and have a low environmental impact.

  Preferably, the decontamination solution contains fruit acid (fruit-derived organic acid such as malic acid, citric acid, tartaric acid, etc.) as the organic acid. For example, this decontamination liquid contains fruit acid alone or other organic acid in addition to fruit acid so that the total amount of organic acid falls within the above range.

  This decontamination solution allows additives or auxiliaries to enhance the cleaning effect. For example, this decontamination solution may contain additives such as amide sulfonic acid, EDTA, NTA-3Na, a surfactant, and amide sulfonic acid.

  Radioactive contaminants to be cleaned with this decontamination solution include all radioactively contaminated items, but for example, tools, piping, parts or equipment used in radiation control areas such as power plants, waste materials or Waste.

  An embodiment of the present invention will be described below with reference to the drawings. FIG. 1 is a flowchart illustrating a method for removing radioactive materials and TOC according to an embodiment of the present invention. FIG. 2 is a block diagram illustrating a radioactive substance and TOC removal apparatus according to an embodiment of the present invention.

  Referring to FIGS. 1 and 2, particularly FIG. 2, a radioactive substance and TOC removing apparatus according to an embodiment of the present invention is an apparatus for removing radioactive substances and TOC from a radioactive liquid waste containing an organic carbon substance. A vacuum distillation pot 4 that distills radioactive waste liquid under reduced pressure in a predetermined atmosphere to fractionate it into a residue and a distillate, a heater (heating means) 4d that heats the inside of the vacuum distillation pot 4 to a predetermined temperature, and a vacuum distillation pot 4 From a vacuum pump (decompression unit) 10 for depressurizing the inside to a predetermined pressure, and from a vacuum distillation kettle 4, from a residue container 5 (residue collecting unit) for collecting a residue containing a radioactive substance together with an organic carbon substance, And a distillate tank (distillate collecting means) 6 for collecting the distillate discharged after the radioactive substance is removed and the organic carbon substance is reduced.

  The vacuum distillation pot 4 is provided with an inlet valve 4 a into which radioactive liquid waste is introduced and a discharge valve 4 b connected to the residue container 5. The upstream of the inlet valve 4a is connected to the radioactive waste liquid tank (radioactive waste liquid supply means) 2 through or without the neutralization tank (neutralization means) 3 shown in FIG.

In particular, referring to FIG. 1, the inlet side of the neutralization tank 3 is connected to the additive tanks 1 a, 1 b,... And the radioactive waste liquid tank 2. From the additive tanks 1a, 1b,..., Various additives are supplied to the neutralization tank 3 or the vacuum distillation kettle 4 as necessary. For example, when the radioactive liquid waste is acidic or alkaline, the radioactive liquid waste is supplied to the neutralization tank 3,
A neutralizing additive is added and mixed to adjust the pH. When the radioactive liquid waste is neutral, the radioactive liquid waste may be directly fed from the radioactive liquid waste tank 2 to the vacuum distillation kettle 4. In addition, the radioactive waste liquid supplied to the vacuum distillation kettle 4 may be a stock solution or may have been subjected to pretreatment such as neutralization and oil removal.

  A stirrer 4 c is provided in the vacuum distillation kettle 4. The stirrer 4c can stir the radioactive waste liquid and scrape the residue toward the discharge valve 4b.

  A heat exchanger 8, a buffer tank 9, and a vacuum pump 10 are connected between the vacuum distillation kettle 4 and the distillate tank 6. The heat exchanger 8 liquefies the vaporized distillate exiting from the vacuum distillation kettle 4. The buffer tank 9 temporarily stores the distillate and prevents sudden occurrence and the like. The vacuum pump 10 reduces the pressure in the distillation pot 4 to a predetermined pressure and maintains the pressure in the buffer tank 9 at about atmospheric pressure. The distillate in the buffer tank 9 may be circulated and supplied to the vacuum distillation kettle 4.

  Subsequently, a method for removing the radioactive substance and the TOC according to the embodiment of the present invention shown in FIG. 1 using the radioactive substance and TOC removing apparatus according to the embodiment of the present invention shown in FIG. 2 will be described. .

  When adjusting the pH of the radioactive liquid waste, the radioactive liquid waste is injected into the neutralization tank 3 from the radioactive liquid waste tank 2 and added to the neutralization tank 3 from the additive tanks 1a, 1b,. Then, the pH-adjusted radioactive liquid waste is introduced into the vacuum distillation kettle 4 through the inlet valve 4a. In the case where the pH of the radioactive liquid waste is not adjusted, the radioactive liquid waste may be put directly into the vacuum distillation kettle 4 from the radioactive liquid waste tank 2. Alternatively, an oil removing agent may be added to the radioactive waste liquid in advance, and the radioactive waste liquid that has been subjected to oil removal treatment may be added to the neutralization tank 3 or the vacuum distillation pot 4.

  Since the inside of the vacuum distillation kettle 4 is depressurized by the vacuum pump 10, the radioactive liquid waste is vaporized at a relatively low temperature, and fractionated into a vaporized distillate and a residue. By containing radioactive substances together with organic carbon substances in the residue, these substances are removed from the vaporized distillate.

  The residue is scraped off by the stirrer 4c and collected in the residue container 5 through the discharge valve 4b. The residue is disposed of because it contains radioactive material. For example, the residue is stored in a predetermined place after being packed in a drum.

  On the other hand, the vaporized distillate is liquefied by the heat exchanger 8 and collected in the distillate tank 6 via the buffer tank 9. From the distillate, radioactive materials have been removed to a non-detectable level, and most of the organic carbon material has also been removed, so that the distillate can be reused in normal or existing facilities. Furthermore, if the filtration filter 7 of FIG. 1 is connected to the distillate tank 6 to adsorb organic carbon substances and the TOC of the distillate is reduced, the distillate can be discharged into public waters such as lakes, rivers, and sea areas. Can do. In addition, since the radioactive liquid is not contained in the distillate, the filtration filter 7 can perform normal waste disposal.

[test]
Using the radioactive substance and TOC removing apparatus according to one embodiment of the present invention described above, according to the radioactive substance and TOC removing method according to one embodiment of the present invention, first, the radioactive liquid waste shown in [0042] as Test 1 The test which removes a radioactive substance and TOC from was performed, and the TOC density | concentration and radioactive contamination density | concentration in obtained distilled water were measured.
In addition, as a test 2, in order to confirm whether or not the present treatment method is effective for cleaning agents other than “Chemia Clean”, a removal test of radioactive substances and TOC by waste liquid using a neutral detergent was performed.
The test conditions of Tests 1 and 2 are as [0042].

・ Radioactive substance and TOC removal device: manufactured by Daiwa Chemical Industry Co., Ltd. ・ Processing capacity of vacuum distillation kettle: 8 to 10 l / H
-Pressure in the vacuum distillation kettle: 0.090-0.096 MPa (Decompression degree: about -4-10%)
・ Temperature in a vacuum distillation kettle: 40-60 ° C
-Accompanying filtration means: carbon filter and multi-stage ion exchange resin-Amount of radioactive waste liquid: 300 liters-Radioactive waste liquid-
・ ・ Test 1: Waste liquid after cleaning the tool used in the radiation control area with the decontamination agent “trade name: Chemia Clean” manufactured by Toden Kogyo Co., Ltd.
“Chemia Clean”: Aqueous decontamination of residual water with 5% total amount of citric acid, malic acid, tartaric acid and formic acid as organic acids ・ ・ Test 2: Tools used in radiation control areas for general washing Waste liquid after washing with neutral detergent ・ Analysis method ・ TOC (total organic carbon): JIS k0101 20

[Test 1]
In accordance with the present invention and the above test conditions, the radioactive waste liquid of Test 1 above (the waste liquid of the organic acid detergent “Chemia Clean” used for decontamination) is subjected to a removal treatment of radioactive substances and TOC, and the TOC concentration in the obtained distilled water and Radioactive contamination concentration was measured. In this test, calcium hydroxide was added as a neutralizing agent before the vacuum distillation treatment. In case 1, up to vacuum distillation treatment was performed, and in case 2, subsequent to case 1, further filtration treatment was performed. The results of Test 1 are shown in Table 1 below.

（注）：「＜」は、３σ法による検出限界値未満を示す [Table 1]

(Note): "<" indicates less than detection limit value by 3σ method

  Referring to Table 1, radioactive substances are substantially completely removed from the obtained distilled water by the vacuum distillation treatment according to the present invention, and the TOC concentration becomes 10 ppm or less, and the TOC is reduced to a reusable level. Removed. Moreover, in addition to this vacuum distillation process, the TOC density | concentration in obtained distilled water became 1 ppm or less by performing a filtration process, and TOC was removed to the level of ultrapure water. In addition, since the removal method and the removal apparatus are completely closed systems and the radioactive contamination concentration on the distilled water side is significantly reduced (substantially completely removed), the radioactive substances in the radioactive liquid waste are It can be seen that it remains on the residue side.

[Test 2]
In accordance with the present invention and the test conditions of [0042], the radioactive waste liquid of Test 2 shown in [0042] was subjected to a treatment for removing radioactive substances and TOC, and the TOC concentration and the radioactive contamination concentration in the obtained distilled water were measured.
In Test 1, since the waste liquid using the organic acid detergent “Chemia Clean” has high acidity and needs to be neutralized, calcium hydroxide is added as a neutralizing agent.
Therefore, in Test 2, in order to confirm whether or not this addition of calcium hydroxide has an effect on the removal of radioactive materials and TOC by the vacuum distillation treatment, the test with and without the addition of calcium hydroxide. The effect was also confirmed.
For this reason, in Case 1, a vacuum distillation treatment is performed, in Case 2, a test in which calcium hydroxide is added (as a neutralizer) before the vacuum distillation treatment in Case 1 is performed, and in Case 3, the vacuum distillation of Case 1 is performed. After the treatment, a filtration treatment was performed. In Case 4, a test was conducted in which calcium hydroxide was added before the vacuum distillation treatment in Case 3. The test results are shown in Table 2 below. The waste liquid before the vacuum distillation treatment was fractionated into about 95% distilled water and about 5% residue (water content 30% or less) by the vacuum distillation treatment.

（注）：「＜」は、３σ法による検出限界値未満を示す
[Table 2]

(Note): "<" indicates less than detection limit value by 3σ method

Referring to Table 2, as in the case of Test 1, the reduced-pressure distillation treatment according to the present invention removes radioactive substances from the distilled water obtained substantially completely, and the TOC concentration becomes 10 ppm or less. The TOC has been removed to a reusable level. Moreover, in addition to this vacuum distillation process, the TOC density | concentration in obtained distilled water became 1 ppm or less by performing a filtration process, and TOC was removed to the level of ultrapure water. In addition, since the removal method and the removal apparatus are completely closed systems and the radioactive contamination concentration on the distilled water side is significantly reduced (substantially completely removed), the radioactive substances in the radioactive liquid waste are It can be seen that it remains on the residue side.
In addition, about the influence of calcium hydroxide, both in the state after vacuum distillation treatment and the state where filtration treatment was applied, both in the case where calcium hydroxide is added and in the case where calcium hydroxide is not added, the TOC concentration and the radioactive contamination concentration. There was no substantial difference (somewhat higher when calcium hydroxide was added). Thereby, it was also confirmed that the addition of calcium hydroxide had no influence on the removal of radioactive substances and TOC by the vacuum distillation treatment and on the removal of TOC by the filtration treatment.

  The present invention relates to a radioactive waste liquid generated from a radiation control area of a nuclear power facility, for example, a nuclear power plant, a nuclear fuel reprocessing facility, a radioactive waste disposal facility, in particular, a radioactive waste liquid decontaminated with a decontamination solution. Applies to processing. In addition, the distillate obtained according to the present invention can be easily treated or reused in a radiation control area or the like. For example, when the distillate is water, it can be treated or reused in an existing water treatment facility. It is.

3 is a flowchart illustrating a radioactive substance and TOC removal method according to an embodiment of the present invention. It is a block diagram explaining the radioactive substance and TOC removal apparatus which concern on one Example of this invention.

Explanation of symbols

1a, 1b, ... Additive tank 2 Radioactive waste liquid tank (radioactive waste liquid supply means)
3 Neutralization tank (neutralization means)
4 Vacuum distillation kettle 4a Inlet valve 4b Residue discharge valve 4c Stirrer 4d Heater (heating means)
5 Residue container (residue collection means)
6 Distillate tank (distillate recovery means)
7 Filtration filter (filtration means)
8 Heat exchanger 9 Buffer tank 10 Vacuum pump (pressure reduction means)

Claims (9)

  A radioactive liquid waste containing an organic carbon substance is distilled under reduced pressure, fractionated into a residue and a distillate, and the radioactive substance is removed by adding the radioactive substance together with the organic carbon substance to the residue, and the organic carbon substance A method for removing radioactive material and TOC, characterized in that the distillate having a reduced content is produced.   The method for removing a radioactive substance and TOC according to claim 1, wherein the TOC concentration of the distillate is 10 ppm or less.   3. The radioactive substance and TOC removal method according to claim 1, wherein the radioactive waste liquid is a waste liquid after decontaminating radioactive contaminants with a decontamination liquid.   The organic carbon substance contained in the residue is added to the organic carbon substance attached to the radioactive contaminant, the organic carbon substance contained in the decontamination liquid from which the radioactive contaminant has been decontaminated, and / or added before the vacuum distillation. The method for removing a radioactive substance and a TOC according to any one of claims 1 to 3, wherein the organic substance is derived from an organic carbon substance contained in the additive.   Before the said vacuum distillation, a neutralizing agent is added according to pH of the said radioactive waste liquid, The component of the said neutralizing agent is contained in the said residue, The radioactive as described in any one of Claims 1-4 characterized by the above-mentioned. Material and TOC removal method.   The radioactive substance and the TOC removing method according to claim 1, wherein the distilled liquid is filtered so that a TOC concentration of the distilled liquid is 1 ppm or less. An apparatus for removing radioactive substances and TOC from radioactive liquid waste containing organic carbon substances,
A vacuum distillation kettle that distills the radioactive liquid waste under reduced pressure to fractionate the residue and the distillate;
Heating means for heating the inside of the vacuum distillation kettle to a predetermined temperature;
Pressure reducing means for reducing the pressure in the vacuum distillation kettle to a predetermined pressure;
A residue collecting means for collecting the residue containing a radioactive substance together with the organic carbon substance from the vacuum distillation pot;
A distillate recovery means for recovering the distillate discharged from the vacuum distillation kettle after the radioactive material is removed and the organic carbon material is reduced;
An apparatus for removing radioactive material and TOC, comprising:   The radioactive substance according to claim 7, further comprising neutralizing means for adding a neutralizing agent in accordance with the pH of the radioactive liquid waste before the vacuum distillation and causing the residue to contain a component of the neutralizing agent. TOC removal device.   The radioactive substance and TOC removing device according to claim 7 or 8, further comprising a filtering means for filtering the distillate to bring the TOC concentration of the distillate to 1 ppm or less.

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