KR20160123806A - Decontamination method for radioactive contamination - Google Patents

Abstract

The present invention relates to a radioactive substance decontamination method capable of decontaminating and removing a radioactive substance, deposited in an internal path, without cutting or disassembling a heat exchanger of a nuclear power plant, having a complex shape, and also conforming to environmental standards by controlling only pH before discharge by decontaminating the radioactive substance through the injection of hydrochloric acid into extracting water. To this end, the method to decontaminate a radioactive substance of a pipe member includes: a step (a) of extracting a radioactive substance, deposited on the inner wall of a path, by circulating the extracting water for the extraction of the radioactive substance through the path of the pipe member; and a step (b) of removing the radioactive substance, contained in the extracting water, after discharging the extracting water from the path of the pipe member.

Description

[0001] DECONTAMINATION METHOD FOR RADIOACTIVE CONTAMINATION [0002]

The present invention relates to a method for decontaminating a radioactive material, and more particularly, to a method for decontaminating a radioactive material immobilized on an inner flow path without removing or breaking a heat exchanger of a nuclear power plant having a complicated shape, The present invention relates to a radioactive material decontamination method capable of complying with environmental standards only by adjusting the pH prior to discharge because hydrochloric acid is injected into the effluent water to decontaminate the radioactive material.

Globally, advanced nations of nuclear power are now at the point of dismantling nuclear facilities that have reached their end of life.

In order to systematically carry out this work, CIDEN was established in France to take charge of dismantlement management. The UK established NDA (Nuclear Facilities Dismantling Business Corporation) in 2005 to establish a comprehensive policy and business plan at national level have.

Korea has also established the Radioactive Waste Management Corporation to systematically manage radioactive waste. Korea has begun to become a practical problem in the dismantling of nuclear power facilities as commercial nuclear power generation started from the late 1970s, and the research reactor TRIGA has been retired.

In order to carry out the dismantling business of nuclear power plants in earnest after 2017, when Kori Unit 1 meets legal life expectancy, preparations such as research and development and securing of relevant technology and establishment of policy direction should be thoroughly carried out from now on.

A large amount of radioactive waste is generated when dismantling nuclear facilities, and the types of metals, concrete, and so on also vary.

Among them, if it is possible to recycle high-quality metals, the amount of waste can be greatly reduced, and the economic and environmental benefits of resource recycling are high, so that the related technologies are being developed in various countries.

On the other hand, as the nuclear facilities are dismantled, radioactive materials attached to the devices to be dismantled are removed before and after dismantling.

Before being dismantled, it is called plant dismantling before dismantling, and it is the main purpose to reduce the dose of radiation at the dismantling work site and reduce the dose of the worker. On the other hand, what is implemented after dismantling is called decontamination after dismantling, and it is aimed to facilitate the storage management of waste and enable reuse of some waste, thereby reducing radioactive waste.

Before the dismantling, the plant decontamination is carried out by bringing the decontamination equipment to the site or replacing the existing equipment. However, after decontamination, the decontamination equipment is brought into the installation place of the decontamination unit In general.

1, a nuclear power plant includes a reactor vessel 101, a primary cooling system 103, a heat exchanger (or steam generator) 105, A secondary cooling system 107, a turbine 109, a generator 111 and a condenser 113. The heat generated by the chain reaction of the fuel in the reactor vessel 101 warms the water on the primary cooling system 103. The heat exchanger (or steam generator) 105 changes the water on the secondary cooling system 107 to steam using the heat energy possessed by the coolant on the primary cooling system 103 and supplies heat to the heat exchanger (or steam generator) The generator 111, which is connected to the turbine 109, generates electric power. The steam passing through the turbine 109 is again cooled with water in the condenser 113 and supplied to the heat exchanger (or steam generator) 105.

As described above, the heat exchanger (or the steam generator) 105 constituting the nuclear power plant is not only exposed to the radioactive material at a high concentration because the water contacting the nuclear fuel in the reactor vessel 101 is circulated, It is difficult to decontaminate before disassembly.

Accordingly, there is a demand for a facility capable of effectively removing radioactive materials before disassembly for a facility having a complicated structure such as a heat exchanger (or a steam generator).

1st Radioactive Waste Treatment Technology Workshop

(Development of Decontamination System for Reactor Cooling System for Dismantling by TRIGA Research)

SUMMARY OF THE INVENTION It is an object of the present invention to solve the above-mentioned problems of the prior art, and it is an object of the present invention to provide a nuclear power plant having a complicated shape without removing or cutting a heat exchanger, The present invention provides a method for decontaminating a radioactive material that can comply with environmental standards only by adjusting the pH prior to discharge because hydrochloric acid is injected into the effluent to decontaminate the radioactive material.

According to another aspect of the present invention, there is provided a method for decontaminating a radioactive material, comprising the steps of: a) circulating the effluent for discharging a radioactive substance through a channel of the tubular member Withdrawing the radioactive material immersed in the inner wall of the channel; And b) removing the radioactive material contained in the discharged water after discharging the discharged water from the flow path of the tubular member.

Preferably, the effluent water contains hydrochloric acid, wherein the concentration of hydrochloric acid is increased every predetermined time, and the maximum concentration of hydrochloric acid is not more than 10%.

Preferably, the step a) includes the steps of: a1) measuring the Fe concentration and the radiation concentration after circulating the evacuation water for a predetermined time; a2) injecting hydrochloric acid into the circulating effluent water, circulating the solution for a predetermined period of time, and measuring Fe concentration and radiation concentration; a3) measuring iron concentration and Fe concentration after additionally injecting hydrochloric acid into the circulating effluent water and circulating for a predetermined time; And a4) a3) the step of repeatedly executes the process; being made, including, if the Fe concentration of the expelled the excess of 0.5%, the radiation concentration of the eviction ¹ × 10 ^- 1 exceeding Bq / g And if the concentration of hydrochloric acid in the effluent exceeds 10%, the step b) is executed.

If the case of more than ¹ Bq / g, acid concentration of the eviction is greater than ^10% and preferably, when the Fe concentration of the expelled the excess of 0.5%, the radiation concentration of the eviction 1 × 10 , The step b) is performed after reversing the number of evacuations in a reverse direction for a predetermined period of time.

Preferably, the predetermined time is 24 hours, and the additional injected hydrochloric acid injected at the a3) is a capacity to increase the hydrochloric acid concentration by 0.5%.

Preferably, in the step a), the evacuation water is injected through a first entrance and exit formed in a lower portion of the tubular member, is discharged through a second entrance formed in a higher part of the tubular member, and then is returned to the first entrance and exit And in the step b), the discharge of the axial flow is discharged through a first inlet and a outlet formed in a lower part of the tubular member, and air is injected into the second outlet.

Preferably, the step b) includes: a first precipitation step of removing cesium and cobalt contained in the evacuation water; And a second settling step of removing the remaining cobalt supplied with the supernatant of the effluent water after the first settling step.

Preferably, the first precipitation step comprises injecting CoCl ₂ into the effluent water so that the Co concentration of the effluent water is 50-200 PPM, and the substituents Na ₄ [Fe (CN) ₆ ] or K ₄ [Fe ( CN) _6] for at least 600 PPM was added to radioactive Co and the non-radioactive Co injection in water expelled Na ⁺ or K ^+, and that replacement and, by 50 ~ 200 PPM injecting CsCl Na ₂ Co [Fe (CN) _6] (Na ₂ Cs ₂ [Fe (CN) ₆ ] or K ₂ Cs ₂ [Fe (CN) ₆ ]) after adjusting the pH to 8.5 to 9.5 by injecting NaOH So as to be precipitated.

Preferably, the second precipitation step comprises adjusting the pH of the effluent water to be 11 to 12; And removing the precipitate to be precipitated.

Preferably, the method further comprises a neutralization step of adjusting HCl to about 6.5 or more and less than 8.5 by injecting HCl into the effluent water after the second precipitation step.

Preferably, after the second precipitation step, the radiation concentration of the waste solution is measured, and if the concentration exceeds the reference value, the first precipitation step and the second precipitation step are repeatedly performed.

Preferably, the tubular member is a waste heat exchanger before decommissioning of a nuclear power plant.

The present invention as described above is advantageous in that the radioactive material deposited on the inner flow path can be decontaminated and removed without decomposing or cutting the heat exchanger of a nuclear power plant having a complicated shape.

In addition, hydrochloric acid is injected into the effluent water to decontaminate the radioactive material, so that it is possible to observe the environmental standards only by adjusting the pH prior to discharge, so that there is an advantage that the post-treatment is simple.

Further, the radiographic density of the number of expelled 1 × 10 ^- Radioactive Particles As ¹ Bq / g for the case of excess, the manner in which the process of by discharging the eviction remove radioactive material repeatedly decontamination process of radioactive materials The treatment is performed in a state in which the concentration of water is not high, which is advantageous in terms of safety.

In addition, the discharge of the discharged water has the advantage of eliminating the accumulation of radioactive sludge accumulated in the inside after circulating the discharged water for a predetermined period of time.

In addition, since the discharged water is circulated from a low portion to a high portion of the heat exchanger, the air inside the flow path can be easily discharged at the initial stage of circulating the discharged water, so that the discharged water is in good contact with the inner wall of the flow path, There is an advantage to increase.

1 is a block diagram schematically showing a configuration of a nuclear power plant.
2 is a flowchart showing a flow of a method for decontaminating a radioactive material according to an embodiment of the present invention.
FIG. 3 is a flowchart illustrating a process of evacuating a method for decontaminating a radioactive material according to an embodiment of the present invention.
4 is a schematic view showing a heat exchanger of a nuclear power plant.

The present invention may be embodied in many other forms without departing from its spirit or essential characteristics. Accordingly, the embodiments of the present invention are to be considered in all respects as merely illustrative and not restrictive.

The terms first, second, etc. may be used to describe various components, but the components should not be limited by the terms.

The terms are used only for the purpose of distinguishing one component from another. For example, without departing from the scope of the present invention, the first component may be referred to as a second component, and similarly, the second component may also be referred to as a first component.

And / or < / RTI > includes any combination of a plurality of related listed items or any of a plurality of related listed items.

It is to be understood that when an element is referred to as being "connected" or "connected" to another element, it may be directly connected or connected to the other element, .

On the other hand, when an element is referred to as being "directly connected" or "directly connected" to another element, it should be understood that there are no other elements in between.

The terminology used in this application is used only to describe a specific embodiment and is not intended to limit the invention. The singular expressions include plural expressions unless the context clearly dictates otherwise.

In the present application, the terms "comprises", "having", "having", and the like are intended to specify the presence of stated features, integers, steps, operations, components, Steps, operations, elements, components, or combinations of elements, numbers, steps, operations, components, parts, or combinations thereof.

Unless defined otherwise, all terms used herein, including technical or scientific terms, have the same meaning as commonly understood by one of ordinary skill in the art to which this invention belongs.

Terms such as those defined in commonly used dictionaries are to be interpreted as having a meaning consistent with the contextual meaning of the related art and are to be interpreted as either ideal or overly formal in the sense of the present application Do not.

Hereinafter, preferred embodiments of the present invention will be described in detail with reference to the accompanying drawings, wherein like or corresponding elements are denoted by the same reference numerals, and a duplicate description thereof will be omitted.

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS Hereinafter, the present invention will be described in detail with reference to the accompanying drawings.

The method of decontaminating a radioactive material according to an embodiment of the present invention is a decontamination method for removing radioactive material deposited in an inner flow path of a tubular member such as a waste heat exchanger before dismantling of a nuclear power plant of FIG.

As shown in FIG. 2, the method of decontaminating the radioactive material comprises the steps of: a) discharging the radioactive material immersed in the inner wall of the channel by circulating the effluent for discharging the radioactive material through the channel of the tubular member, and b) And discharging the effluent from the flow path of the member, and removing the radioactive material contained in the effluent water.

Specifically, the discharged water functions to circulate through the internal flow path of the waste heat exchanger of the nuclear power plant, which is the tubular member, and be discharged to the radioactive material immersed on the internal flow path. It is preferable that the evacuation water contains hydrochloric acid and the maximum concentration does not exceed 10%, because if the concentration of hydrochloric acid exceeds 10%, the metal component of the tubular member is excessively extracted by the effluent water to be.

The step a) comprises: a1) measuring the Fe concentration and the radiation concentration after circulating the evacuation water for a predetermined time, a2) injecting hydrochloric acid into the circulating effluent water, circulating the circulating effluent water for a predetermined time, measuring the Fe concentration and the radiation concentration A3) adding hydrochloric acid to the circulating effluent water, circulating the solution for a predetermined time, measuring the Fe concentration and the radiation concentration, and a4) repeating a3).

4 (A) or (A2)) formed at a lower portion of the tubular member to form a second doorway (FIG. 4 (a)) formed at a higher portion of the tubular member, B1 or B2, and then injected again into the first doorway.

This is to allow the discharged water to be discharged to a higher position while gradually getting out from the lower part, so that the discharged water can be filled in the inside of the flow path without filling the inside of the flow path.

In the step a1), the effluent water made of pure water is circulated for 24 hours to circulate the internal flow path of the waste heat exchanging apparatus, thereby discharging impurities in the flow path, and determining whether or not the flow path is cracked.

On the other hand, when the Fe concentration of the evacuation water exceeds 0.5% or the radiation concentration of the evacuation water exceeds 1 x 10 < ^-1 > Bq / g after measuring the Fe concentration and the radiation concentration of the evacuation water after 24 hours, ), Otherwise proceed to step a2).

In step a2), hydrochloric acid is injected into the effluent water, and the amount of the injected hydrochloric acid is such that the concentration of hydrochloric acid in the effluent water is 0.5%.

Hydrochloric acid is injected and circulated for 24 hours to additionally remove the radioactive material adhering to the inner flow path of the waste heat exchange apparatus.

On the other hand, when the Fe concentration of the evacuation water exceeds 0.5% or the radiation concentration of the evacuation water exceeds 1 x 10 < ^-1 > Bq / g after measuring the Fe concentration and the radiation concentration of the evacuation water after 24 hours, ), Otherwise proceed to step a3).

In step a3), hydrochloric acid is additionally injected into the effluent, and the amount of the injected hydrochloric acid is a capacity to increase the hydrochloric acid concentration of the effluent water by 0.5%.

Hydrochloric acid is additionally injected and then circulated for 24 hours to additionally remove the radioactive material adhering to the inner flow path of the waste heat exchange apparatus.

On the other hand, when the Fe concentration of the evacuation water exceeds 0.5% or the radiation concentration of the evacuation water exceeds 1 x 10 < ^-1 > Bq / g after measuring the Fe concentration and the radiation concentration of the evacuation water after 24 hours, ). Otherwise, a3) is repeatedly executed.

Specifically, hydrochloric acid is additionally injected so that the concentration of hydrochloric acid in the effluent water is increased by 0.5%, and the Fe concentration and the radiation concentration of the effluent water are measured after circulating for 24 hours. When the Fe concentration of the effluent water exceeds 0.5% the radiation concentration of the eviction 1 × 10 ^- when it is more than ¹ Bq / g run the step b), otherwise it will continue to repeat.

At this time, the concentration of hydrochloric acid gradually increases as the step a3) is repeatedly performed. It is preferable that the maximum concentration of hydrochloric acid does not exceed 10%, and if the concentration of hydrochloric acid becomes excessively high, Is excessively large and post-treatment is difficult.

As a result, the a1) to a4) if it exceeds the eviction number of Fe concentration is 0.5% of the traveling steps, the radiation concentration of the eviction 1 × 10 ^- if it exceeds ¹ Bq / g, the eviction And the concentration of hydrochloric acid in water exceeds 10%, the step (b) is executed.

Meanwhile, in step b), it is preferable that the discharge of the axial flow is discharged through a first inlet / outlet formed in a lower portion of the tubular member and air is injected into the second outlet / outlet, It can be discharged naturally to the first entrance and exit, and at the same time, the smooth discharge can be induced by the air injected into the second entrance.

Meanwhile, it is preferable to carry out the step b) after reversing the evacuation number in the reverse direction for a predetermined time before executing the step b), because the reason for removing the accumulated radioactive sludge .

As described above, the step b) of removing the radioactive material contained in the discharged water discharged from the waste heat exchanger before the dismantling of the nuclear power plant through the step a) will be described.

The step b) includes a first precipitation step of removing cesium and cobalt contained in the effluent water and a second precipitation step of removing cobalt remaining in the supernatant of the effluent water after the first precipitation step .

Specifically, in the first precipitation step, CoCl ₂ is injected into the effluent water to adjust the Co concentration of the effluent water to 50-200 PPM (the capacity is controlled according to the Fe concentration), and K ₄ [Fe (CN) ₆ ] or Na ₄ [Fe (CN) ₆ ] at least 600 PPM to allow K ⁺ or Na ⁺ to be substituted with Co (see first reaction scheme).

(First reaction formula)

K ₄ [Fe (CN) ₆ ] + CoCl ₂ -> K ₂ Co [Fe (CN) ₆ ] + 2KCl

Na ₄ [Fe (CN) ₆ ] + CoCl ₂ -> Na ₂ Co [Fe (CN) ₆ ] + 2KCl

After replacing the substituent K ⁺ or Na ⁺ with Co, at least 200 PPM of CsCl is added so that Co of the substituent is substituted with Cs (see the second reaction scheme).

(Second reaction formula)

K ₂ Co [Fe (CN) ₆ ] + ₂ CsCl -> K ₂ Cs ₂ [Fe (CN) ₆ ] + CoCl ₂

Na ₂ Co [Fe (CN) ₆ ] + ₂ CsCl -> Na ₂ Cs ₂ [Fe (CN) ₆ ] + CoCl ₂

Mixing is performed for 2 hours or more so that sufficient substitution can be made. When the substitution is completed, the pH is adjusted to 8.5 to 9.5 by injecting NaOH to facilitate precipitation.

After pH adjustment, rapid stirring is performed for 30 minutes or more, then low speed stirring is performed for 2 hours or more and then left for 24 hours so that sufficient precipitation is performed.

The pH is adjusted to 8.5 to 9.5 in order to facilitate the precipitation, and the addition of at least 600 PPM of the substituent is required to substitute and precipitate as much Co and Cs as possible. to be.

Since most of the radioactive materials are metal elements and more than 99% of the radioactive materials are composed of Co60 (80% ~ 90%) and Cs137 (10 ~ 20%), solution of non-radioactive Co and substituted Jane _{Na 4 [Fe (CN) 6} ] for injection by and replaced with _{Na 2 Co [Fe (CN)} 6] in accordance with the ionization tendency, by injecting _{Cs Na 2 Cs 2 [Fe (} CN to ) ₆ ].

As described above, the substituted Na ₂ Co [Fe (CN) ₆ ] and Na ₂ Cs ₂ [Fe (CN) ₆ ] solution are co-precipitated at pH 8.5 to 9.5 by injecting NaOH, ⁺ Ions bind to Co (OH) ₂ at pH 11 ~ 12 with NaOH and precipitate.

When these contents are represented by chemical equations,

(1) Extraction of radioactive material

M + HCl -> MCl ₂ + H ₂ O + HCl

Co + HCl -> CoCl ₂ + H ₂ O + HCl

(Where M is Fe, Co, Cs, etc.)

(2) Non-radiation CoCl2 injection and substitution injection

CoCl ₂ + H ₂ O + HCl + Na ₄ [Fe (CN) ₆ ]

-> Na ₂ Co [Fe (CN) ₆ ] + FeCl ₂ + H ₂ O + HCl

(3) Non-radiation CsCl injection

Na ₂ Co [Fe (CN) ₆ ] + FeCl ₂ + H ₂ O + HCl + ₂ CsCl

_{-> Na 2 Co [Fe (} CN) 6] + Na 2 Cs 2 [Fe (CN) 6] + FeCl 2 + CoCl 2 + HCl + H 2 O

(4) NaOH injection (pH 8.5 to 9.5)

Na ₂ Co [Fe (CN) ₆ ] + Na ₂ Cs ₂ [Fe (CN) ₆ ] + FeCl ₂ + CoCl ₂ + NaOH

- + Na ₂ Co [Fe (CN) ₆ ] + Na ₂ Cs ₂ [Fe (CN) ₆ ] + Fe (OH) ₂ + Co (OH) ₂ + NaCl + FeCl ₂ + CoCl ₂ + H ₂ O + NaOH

(5) NaOH injection (pH 11-12)

FeCl ₂ + CoCl ₂ + H ₂ O + NaOH + NaCl

-> Fe (OH) ₂ + Co (OH) ₂ + NaCl + NaOH + H ₂ O

The non-radioactive cobalt salt may be CoCl ₂ . In practice radioactive waste liquid Co ^{2 +} concentration is very low in remaining in the, by the addition of non-radioactive cobalt salt it should keep the concentrations of Co ²⁺ in the radioactive waste liquid so constant. This is because, if the concentration of Co ²⁺ in the radioactive waste solution of the first reaction formula is higher than a certain level, K ₂ CoFe (CN) ₆ is formed which can sequentially take place in the second and third reaction schemes .

The second precipitation step of removing the remaining cobalt after receiving the supernatant of the effluent water through the first precipitation step as described above will be described.

And the second precipitation step comprises adjusting the pH of the effluent water to be at least 11 to 12 and removing the precipitate to be precipitated.

Since the cobalt may still remain in the effluent water after the first precipitation step, the pH is adjusted to 11 to 12 so that the cobalt component can be precipitated.

By adjusting the pH, the cobalt component is precipitated as shown in the following reaction formula.

FeCl ₂ + CoCl ₂ + NaOH -> Fe (OH) ₂ ↓ + Co (OH) ₂ ↓ + NaCl + NaOH

Meanwhile, after the second precipitation step, if the radiation concentration of the outflow water is measured and exceeds the radioactive reference value capable of discharging, the first precipitation step and the second precipitation step may be repeatedly performed, And then discharges the radioactive material.

Meanwhile, as described above, after the first precipitation step and the second precipitation step, there is further included a neutralization step of adjusting the pH to 6.5 or more and less than 8.5 by injecting HCl into the effluent water before discharging the effluent water .

On the other hand, the precipitate precipitated in the above may be evaporated and dried to reduce its weight, and then stored in a separate radioactive material reservoir.

Although the present invention has been described with reference to the preferred embodiments thereof with reference to the accompanying drawings, it will be apparent to those skilled in the art that many other obvious modifications can be made therein without departing from the scope of the invention. Accordingly, the scope of the present invention should be interpreted by the appended claims to cover many such variations.

Claims (12)

A method for decontaminating a radioactive material in a tubular member in which a radioactive substance is immersed,
a) discharging the radioactive material immersed in the inner wall of the channel by circulating the effluent for discharging the radioactive material through the channel of the tubular member; And
b) removing the radioactive material contained in the effluent after discharging the effluent from the channel of the tubular member. The method according to claim 1,
Wherein the effluent water contains hydrochloric acid, the concentration of hydrochloric acid is increased every predetermined time, and the maximum concentration of hydrochloric acid is not more than 10%. The method according to claim 1,
The step a)
a1) measuring the Fe concentration and the radiation concentration after circulating the evacuation water for a predetermined time;
a2) injecting hydrochloric acid into the circulating effluent water, circulating the solution for a predetermined period of time, and measuring Fe concentration and radiation concentration;
a3) measuring iron concentration and Fe concentration after additionally injecting hydrochloric acid into the circulating effluent water and circulating for a predetermined time; And
a4) repeating a3) process,
If the Fe concentration of the expelled the excess of 0.5%, the radiation concentration of the eviction 1 × 10 ^- if it exceeds ¹ Bq / g, at least any of when a hydrochloric acid concentration of the eviction exceeds 10% Wherein the step b) is carried out if the radioactive material is in one case. The method of claim 3,
If the Fe concentration of the expelled the excess of 0.5%, the radiation concentration of the eviction 1 × 10 ^- if it exceeds ¹ Bq / g, at least any of when a hydrochloric acid concentration of the eviction exceeds 10% And if it is determined that the number of expulsion is equal to or greater than a predetermined value, reversing the number of evacuations in a reverse direction for a predetermined time, and then performing the step b). The method of claim 3,
Wherein the predetermined time is 24 hours, and the additional injected hydrochloric acid injected at the a3) is a capacity to increase the hydrochloric acid concentration by 0.5%. The method according to claim 1,
In the step a), the exhaled water is injected through a first doorway formed at a lower portion of the tubular member, discharged through a second doorway formed at a higher portion of the tubular member, and then injected again into the first doorway And,
Wherein, in step (b), the discharge of the axial flow is discharged through a first outlet formed in a lower portion of the tubular member, and air is injected into the second outlet. The method according to claim 1,
The step b)
A first precipitation step of removing cesium and cobalt included in the evacuation water; And a second precipitation step of removing the remaining cobalt supplied with the supernatant of the effluent water after the first precipitation step. 8. The method of claim 7,
Wherein the first precipitation step comprises:
CoCl ₂ is injected into the effluent water so that the Co concentration of the effluent water is 50-200 PPM and at least 600 PPM of Na ₄ [Fe (CN) ₆ ] or K ₄ [Fe (CN) ₆ ] (Co) of Na ₂ Co [Fe (CN) ₆ ] is replaced with Cs by injecting 50 to 200 PPM of CsCl and the non-radioactive Co in the effluent water is replaced with Na ⁺ or K ⁺ (Na ₂ Cs ₂ [Fe (CN) ₆ ] or K ₂ Cs ₂ [Fe (CN) ₆ ]) is precipitated after adjusting the pH to 8.5 to 9.5 Way. 8. The method of claim 7,
Wherein the second precipitation step comprises:
Adjusting the pH of the evacuation water to be 11 to 12; And removing the precipitate to be precipitated. ≪ RTI ID = 0.0 > 11. < / RTI > 8. The method of claim 7,
After the second precipitation step,
And a neutralization step of injecting HCl into the effluent water to adjust the pH to not less than 6.5 and less than 8.5. 8. The method of claim 7,
After the second precipitation step,
Measuring the radiation concentration of the waste solution, and repeating the first precipitation step and the second precipitation step when the concentration exceeds the reference value. The method according to claim 1,
Wherein the tubular member is a waste heat exchanger before decommissioning of a nuclear power plant.

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