KR100893680B1 - Removing method of radioactive containment in air and apparatus using the same - Google Patents

Abstract

A removing method of radioactive containment in air and apparatus using the same is provided to protect an inner clothing of a worker by removing tritium in air through humidification and dehumidification. A removing method of radioactive containment in air and apparatus comprises a local humidifier(4) and a local dehumidifier(18). The local dehumidifier catches moisture contacted with tritium and HTO and it process the caught moisture, and the local humidifying unit comprises the local humidifier(10), a water tank(12), and a pump(16). The radioactive detector senses the radioactive pollution concentration of the dehumidification water stored in the dehumidification water storage tank.

Description

REMOVING METHOD OF RADIOACTIVE CONTAINMENT IN AIR AND APPARATUS USING THE SAME}

The present invention relates to an apparatus and a method for removing radioactive pollutants in air, and more particularly, in a nuclear power plant contaminated with tritium and discharged contaminated air into the atmosphere, through humidification and dehumidification. The present invention relates to a device for removing radioactive pollutants in the air and a method of removing the radioactive pollutant concentration.

As coolant and moderator in general pressurized heavy water reactor type nuclear power plant, the median is (D ₂ O) is used. Some of the above-described and the median is, combined with a neutron during the output operation of the reactor is generated by a radiation replaced with tritium (T or ³ H). Its concentration increases with increasing plant operating life.

The heavy water is leaked through evaporation from a pipe or a pump seal, etc. At this time, tritium is also leaked to exist in the form of steam (moisture) in the air. Tritium, which leaks and is present in the form of moisture, emits low energy beta rays, in particular, and enters the body through the breathing or skin of workers, causing internal exposure.

Accordingly, in a heavy water reactor type nuclear power plant using heavy water as a coolant and a moderator, various methods are implemented to prevent exposure of work workers to tritium.

One of the methods mentioned above is a device using the characteristic that tritium is well absorbed by water. Most of these devices include direct injection of tritium-containing air into water, contact with water, humidification with a humidifier to tritium-containing air, or spraying with tritium in air containing tritium. .

In addition to the devices described above, a method of compressing and condensing air or removing tritium, which is a radioactive pollutant, in a region using a bubbler is also used.

Some of the above devices must increase the moisture concentration in the air inside the nuclear power plant. In order to increase the moisture concentration in the air, a method of spraying and humidifying with a nozzle, a method of evaporating water with heat, a method of humidifying with ultrasonic waves, a method of receiving through a steam pipe, and the like are used.

After the humidification as described above, tritium in the air is treated through dehumidification. Examples of the dehumidification methods include a passage through a water adsorbent, a passage through a cooling coil flowing through a refrigerant, a method of compressing air, and a centrifugal separation or inertial separation during injection, and a method of compressing air and spraying the cooling plate. As the moisture adsorbent, silica gel, activated alumina, molecular sieves and the like are used.

However, when a tritium bubbler is used, tritium is difficult to remove sufficiently only by contact with the above water. In particular, the water in contact with tritium also contains tritium. That is, tritium is difficult to remove because water to be absorbed by tritium is released into tritium again while being evaporated into the air in contact with air.

In order to solve this problem, in some cases, a high-efficiency HEPA filter or a moisture adsorbent may be added to allow the air to be discharged after passing through water and then dried. However, the adsorbent has a problem that can not perform any more function when the water adsorbed therein reaches a saturated state.

In particular, methods such as humidification and watering increase the amount of moisture close to saturation, and thus, it is difficult to maintain the performance of the adsorbent and thus cannot remove the tritium contained in the air completely.

In addition, before the air in contact with water is treated with an adsorbent, a process of performing cooling and dehumidification by passing a cooling coil through which a refrigerant flows may be further performed. This also has a limitation in treating moisture by cooling dehumidification. In particular, since a large amount of water is contained in the air after the cooling dehumidification process, it is difficult to maintain the performance of the adsorbent for a long time, there is a problem that the adsorbent should be replaced frequently.

Meanwhile, in order to lower the level of radioactive contamination in the air inside the nuclear power plant and to safely operate the nuclear power plant, a certain amount of air is discharged to the outside to maintain the pressure inside the reactor building at a lower pressure than atmospheric pressure.

When the air in the nuclear power plant is discharged to the outside, the air is discharged through the intermediate filter, the HEPA filter, and the activated carbon filter in this order. However, since tritium is difficult to collect, there is a problem in that the surrounding area is polluted by being released into the atmosphere without any special measures.

In order to solve such a conventional problem and to remove the exposure by tritium, the heavy water reactor-type nuclear power plant is equipped with a removal facility capable of removing tritium from the air.

The tritium removal system is composed of one large system (D ₂ O Vapor Recovery System) which simultaneously removes tritium and moisture in each region.

As a method of removing tritium using tritium removal equipment, the moisture (including tritium) in air is adsorbed using a desiccant agent, and when the desiccant is saturated, the desiccant is dried using heat and used again. There is a method using the adsorption and separation phenomenon. In addition, there is a method of removing tritium by introducing air containing tritium into the water.

When tritium, a radioactive substance that emits low energy beta rays, exists in the vapor state in the air, it enters the body through the breathing action of the worker or through the skin. Due to this, tritium absorbed by the human body has a problem that may adversely affect worker health by spreading quickly throughout the body.

In particular, pressurized deuterium-type nuclear power plants generate a large amount of tritium. Accordingly, when the air inside the power plant contaminated with tritium is released into the general atmosphere through the air conditioning system, there is a problem of polluting the atmospheric environment around the nuclear power plant.

The present invention has been proposed in order to solve the problems of the prior art, an object of the present invention, radioactivity through the humidification and dehumidification of the radioactive material of the nuclear power plant, in particular the area contaminated by tritium and polluted air in the air discharge To reduce the concentration of pollution.

Another object of the present invention is to reduce the radioactive pollution concentration in a power plant by treating air contaminated by air, particularly tritium, in a nuclear power plant through humidification and dehumidification.

In order to achieve the above object, the present invention provides a device for removing radioactive pollutants in air for reducing the concentration of tritium in air contaminated with tritium, which is a radioactive material in a nuclear power plant, wherein the concentration of moisture in the air inside the nuclear power plant is reduced. The local humidifier is installed to increase the, and the local dehumidifier is installed so as to collect and process the moisture in contact with tritium and HTO in the air by the humidification of the local humidifier.

In addition, the present invention is a device for removing radioactive pollutants in the air to reduce the tritium concentration in the process of discharging air contaminated with tritium, which is a radioactive material in a nuclear power plant, to the air discharge means to increase the moisture concentration. Humidification means is installed, the dehumidification means installed in the air discharge means to collect the moisture in contact with tritium and HTO in the air by the humidification of the humidification means, and through the control and sensing means of the humidifying means and dehumidifying means Control means for determining whether the removal target value for the tritium in the air is exceeded, and by distributing air to the atmosphere according to the control means signal to the atmosphere according to whether the tritium removal target value of the air passed through the humidification means and dehumidification means It characterized in that it comprises a duct opening and closing means to be installed.

According to the present invention, it is possible to drastically reduce the concentration of tritium in the air by continuously humidifying and dehumidifying the air contaminated area with radioactive material. In addition, by repeatedly operating the humidification and dehumidifying apparatus and distributing the amount of discharged air, the degree of pollution of tritium in the discharged air can be lowered to a desired target value.

In addition, when the radioactive material of the nuclear power plant, in particular, the discharge of air polluted by tritium, there is an effect that can reduce the radioactive pollution concentration through the humidification and dehumidification in the treatment duct.

In addition, when the radioactive material of a nuclear power plant, in particular, the area polluted by tritium and polluted air is discharged to the atmosphere, the tritium is removed by dehumidifying the moisture in contact with the pollutant after increasing the moisture concentration by humidification. There is an effect that can prevent the worker's internal exposure.

DESCRIPTION OF THE PREFERRED EMBODIMENTS Hereinafter, preferred embodiments of the present invention will be described in detail with reference to the accompanying drawings (the same components as in the prior art are given the same reference numerals).

The radioactive pollutant removal device in the air according to the present invention, as shown in Figure 1, by spraying the OH radicalized water through the catalytic action inside the nuclear power plant (2) contaminated with tritium, a radioactive material A local humidifier 4 is provided as a humidification means for increasing the moisture concentration in the air. The OH radicalization of the water for humidification is to increase the collection efficiency of tritium and tritium compounds in the air.

In the regional humidifier 4, a plurality of local humidifiers 10 are installed on the ceiling so as to be sprayed inside the reactor building 6 and the auxiliary building 8. The regional humidifier 10 is adapted to spray water together with compressed air through one or more nozzles.

The local humidifier 10 is connected to the water storage tank 12 by a pipe 14 so that purified water can be supplied. The water in the water storage tank 12 is supplied to the local humidifier 10 at a high pressure by the pump 16. In addition, the water stored in the water storage tank 12 is OH radicalized through the following catalysis.

The catalyst is a substance which does not change itself in a chemical reaction and changes the reaction rate or initiates the reaction.

Photocatalyst, which is a kind of the catalyst, refers to the catalysis taking place with light energy. Representative photocatalysts include ZnO, CdS, WO₃, TiO₂, among which TiO₂ has the best activity.

When irradiated with ultraviolet rays in water, TiO₂, a catalyst having semiconductor properties, is energetically excited and released electrons react with dissolved oxygen or hydrogen peroxide in water to form OH radicals. Radicals are formed.

The catalytic reaction is shown in stages as follows.

1. TiO₂ catalyst reaction process by UV

TiO₂ + hv → e ^_ (emission) + h (TiO₂ surface)

2. The reaction of electrons

e ^_ + O₂ → O ₂ ^_ (super oxide radical)

2O ₂ ^_ + 2H₂O → 2OH + 2OH ^_ + O₂

3. Total catalytic reaction

h ⁺ + OH ^_ → 2OH

Titanium dioxide can be used semi-permanently because it does not change even when it receives light (ultraviolet rays). In addition, it produces oxidizing hydroxyl radicals, which are 20.07 times higher than chlorine (Cl ₂ ) and 1.16 times higher than ozone (O ₃ ).

The tritium in the air easily bonds with the water particles of the OH radicalized moisture, and when the moisture concentration is increased by humidification, the tritium in the air has a high probability of contacting the moisture in the air, thereby making a large water molecule. This large water molecule facilitates dehumidification.

In the reactor building 6 and the auxiliary building 8 in which the local humidifier 4 is installed, the local dehumidifier 18, which is a dehumidification means for collecting and treating moisture in contact with tritium and HTO in the air, is placed on the floor. It is installed.

In the regional dehumidifier 18, a plurality of local dehumidifiers 20 are installed at the bottom to dehumidify the inside of the reactor building 6 and the auxiliary building 8. The regional dehumidifier 20 is provided with cooling coils (not shown) through which refrigerant flows, and condenses by dehumidifying when moisture containing tritium passes.

In addition, a dehumidifying water storage tank 22 in which the dehumidified dehumidified water is stored is connected to the local dehumidifier 20 by a pipe 24. The dehumidifying water storage tank 22 is provided with a radioactive sensor 30 to detect the radioactive contamination concentration of the dehumidified water stored. When the radioactive contamination concentration of the dehumidified water is less than the reference value, the radioactive detector 30 classifies the general waste. The general waste is discharged through the outlet 26 of the dehumidifying water storage tank 22. When the radioactive contamination concentration of the dehumidified water is equal to or greater than the reference value, it is stored and stored in the liquid radioactive waste storage tank 28 connected to the dehumidified water storage tank 22.

The operation of the area humidifier 4 and the area dehumidifier 18 is controlled by the control unit 32, which is a control means into which control information is input.

The control unit 32 controls the pump 16, the humidifier 10, the dehumidifier 20, the radioactive sensor 30, and the like so as to provide proper humidification and dehumidification. Proper humidification and dehumidification control is controlled by the control unit according to the result of measuring the amount of water to be dehumidified or the amount of proper humidity in the air.

Hereinafter, the operation of the present invention through the radioactive pollutant removal device in the air made as described above.

First, the control unit 32 is operated to remove tritium in the reactor building 6 and the auxiliary building 8. The pump 16 acting as a signal of the control unit 32 pumps water stored in the water storage tank 12 by being purified and OH radicalized.

The pumped water travels through the pipe 14 to the humidifier 10. The humidifier 10 sprays water into the reactor building 6 and the auxiliary building 8 by a signal from the controller 32 to humidify (S110).

The humidifier 10 which sprays water is installed in the ceiling inside a building, and humidifies the inside of the reactor building 6 and the auxiliary building 8 whole. The moisture concentration is increased by the humidification of the reactor building 6 and the auxiliary building 8.

The moisture sprayed from the humidifier 10 comes into contact with tritium contained in the air inside the reactor building 6 and the auxiliary building 8 (S120). Moisture in contact with the tritium is collected (S130) by the dehumidifier 20 operating by the signal of the control unit 32. The moisture collected in the dehumidifier 20 is condensed and dehumidified when passing through the cooling coil in which the refrigerant flows inside the dehumidifier 20.

The dehumidifying water dehumidified by the dehumidifier 20 is stored in the dehumidifying water storage tank 22.

The radioactive detector 30 installed in the dehumidifying water storage tank 22 measures the concentration of tritium in the dehumidifying water using the control unit 32 signal (S150). If the tritium concentration measured by the radioactive sensor 30 is less than the reference value, it is a safe state and discharged through the outlet 26, and if the tritium is above the reference value, it is determined that the liquid radioactive waste radioactive waste storage tank (28) Store processing (S160).

의 시간당 제염 효율을 갖게 되며, 오염된 구역의 n회 가습후 제습될 경우 (1-e)ⁿ의 제염효율을 갖게 된다.As described above, when humidification and dehumidification are continuously operated in an air-contaminated area, for example, when the dehumidification efficiency of the dehumidifier is called 'e' and the amount of dehumidification air is Ma / h, the air is kept in a predetermined space. Tritium concentration in water is determined by

It will have decontamination efficiency per hour, and if it is dehumidified after n times of contaminated area, it will have decontamination efficiency of (1-e) ⁿ.

Accordingly, the humidification and dehumidification apparatus can lower the tritium contamination in the air to a desired target value when properly designed. For example, with a dehumidification efficiency of 70%, the degree of contamination is reduced by (1-0.7) ^{3 in} three cycles of circulation.

In the above, the removal of tritium, which is a radioactive pollutant, has been described in the contaminated area inside a nuclear power plant.

Hereinafter, a method and apparatus for removing tritium in the process of discharging radioactive contaminants into the air will be described.

In nuclear power plants, not only local contaminant removal in the plant, but also for the safe operation of the nuclear power plant, the pressure inside the reactor building must be maintained at a lower pressure than atmospheric pressure to prevent the release of airborne radioactive material to the outside. .

In order to maintain the low pressure inside the reactor building, it is necessary to discharge a certain amount of air from the power plant to the outside through the treatment duct.

The present invention can also be applied when releasing a certain amount of contaminated air through the treatment duct.

The apparatus for removing radioactive pollutants in the air includes a processing duct 50 which is an air discharge means installed in a nuclear power plant, as shown in FIGS. 3 and 4.

The treatment duct 50 is supplied with air from which radioactive particles and radioactive inert gas have been removed.

The treatment duct 50 to which the discharge gas is supplied is provided with a first valve 54 for opening the duct, and thereafter, a first tritium detector 56 which is one of the sensing means to detect tritium in the air. Is installed.

In addition, the processing duct 50 provided with the first tritium detector 56 is provided with a first H ₂ O monitor 58 which is one of the sensing means to detect H ₂ O in the flowing air.

The processing duct 50 in which the first H ₂ O monitor 58 is installed is also provided with a flow meter 60 which is one of the sensing means to detect the amount of air flowing therein.

In the processing duct 50 in which the first H ₂ O monitor 58 is provided, a preheater 64 serving as a heating means is provided to heat the flowing air by the signal of the temperature regulating device 62. The preheater 64 is a heating device for increasing the moisture concentration in the air or for improving the moisture saturation in the air.

In the treatment duct 50 in which the preheater 64 is installed, a humidifier 68 is provided at regular intervals so as to spray water from the water storage tank 66 into the flowing air.

The humidifier 68 is formed of a plurality of nozzles to spray the OH radicalized water in the air heated by the preheater 64.

In addition, the processing duct 50 in which the humidifier 68 is installed is provided with a stirrer 70 for easily mixing air and moisture after the humidifier.

The dehumidifier 72, which is a dehumidifying means made of a cold plate coil, is installed in the processing duct 50 in which the stirrer 70 is installed.

The treatment duct 50 in which the dehumidifier 72 is installed is provided with a second tritium detector 74 which is one of the sensing means to detect the tritium in the air passing through the dehumidifier 72.

A second H ₂ O monitor 76, which is one of the sensing means, is also installed to detect moisture in the air passing through the dehumidifier 72.

The flap door 78 which is a duct opening-and-closing means which controls the flow path of the air which passed through the dehumidifier 72 is provided. The flap door 78 selects any one of the recirculation duct 80 and the discharge duct 82 branched by a signal of a control unit which is a control means to block and open.

The recirculation duct 80 is in communication with the inlet of the treatment duct during the opening of the flap door 78 and the second valve 84 so that the recirculation duct 80 is recirculated when the air having completed the tritium removal process in the air is above the reference value.

In addition, the discharge duct 82 is formed to communicate with the outside during the opening of the flap door 78 and the third valve 86. The discharge duct 82 is discharged to the atmosphere when the air after the tritium removal process in the air is less than the reference value. The discharge duct 82 is provided with a tritium monitor 88, which is one of the detection means capable of detecting tritium in the air finally discharged.

On the other hand, the dehumidifier 72, the dehumidification water storage tank 90 for storing the dehumidified dehumidified water is connected. The dehumidifying water storage tank 90 is provided with a tritium monitor 92 which is one of the sensing means so as to measure the tritium concentration in the dehumidifying water to be stored.

Further, the dehumidifying water storage tank 90 is provided with a waste storage tank 94 for storing radioactive waste and an outlet 96 for discharging general waste.

Then, when the tritium concentration of the dehumidified water is less than the reference value is discharged to the general waste through the discharge port 96, if it is above the reference value is separated into liquid radioactive waste is processed to be stored in the waste storage tank 94.

As described above, the apparatus for removing radioactive pollutants in the air is controlled by a signal from the controller 95. In addition, detection means such as the first tritium detector 56, the first H ₂ O monitor 58, the second tritium detector 74, the second H ₂ O monitor 76, the tritium monitor 92 and the like Silver is installed in the duct that is the air discharge means is not limited to the installation position if it is necessary to detect the tritium concentration and moisture in the air.

Hereinafter, the effect | action of this invention made as mentioned above is demonstrated.

First, the air is discharged through the treatment duct 50 by operating a control unit to drive the air pollutant removing device installed in the treatment duct 50 to air inside the reactor building and the auxiliary building.

 At this time, the air discharged through the treatment duct 50 is air contaminated with radioactive material in the nuclear power plant.

The contaminated air passes through the first tritium detector 56, the first H ₂ O monitor 58, and the flow meter 60 after passing through the first valve 54. Accordingly, the controller 95 may detect the tritium concentration in the introduced air through the first tritium detector 56 (S210).

The first H ₂ O monitor 58 detects moisture concentration in the air, and the flow meter 60 detects the amount of air introduced therein.

The sensing information such as tritium concentration, moisture concentration, and air amount is provided to the control unit 95, and the control unit 95 determines the provided information so as to appropriately control the temperature control device 62 and the preheater 64. do.

Accordingly, the preheater 64 increases the moisture concentration in the air by heating the air passing through (S220). The air heated by the preheater 64 is OH radicalized in contact with the moisture that is properly sprayed (S230) in the humidifier 68 in accordance with the amount of humidity in the air. OH radicalized moisture makes it easy to capture tritium and tritium compounds in the air.

Thereafter, the tritium in the moisture and the air is agitated (S240) by the stirrer 70, whereby the moisture and the air are well mixed and the tritium and the bonding force in the air are increased. Moisture combined with tritium in the air is dehumidified by the dehumidifier 72 (S250). That is, dehumidification of moisture is carried out while condensing when the refrigerant passes through the cooling plate coil.

The dehumidified water dehumidified as described above is stored in the dehumidified water storage tank 90, and the tritium concentration is measured by the first tritium monitor 92. If the measurement result of the tritium concentration is less than the target value is discharged as a general waste through the discharge port 96, if it is above the reference value is classified as a liquid radioactive waste and stored in the waste storage tank 94 (S260).

Meanwhile, the second tritium detector 74 and the second H ₂ O monitor 76 provide information to the controller 95 by detecting the concentration of tritium and moisture contained in the air passing through the dehumidifier 72. .

The controller 95 receiving the above-mentioned information causes the flap door 78 to block the recirculation duct 80 when the concentration of tritium in the air is equal to or lower than the target value, and vice versa through the open duct 82 (S270). )

The air discharged through the discharge duct 82 is discharged to the atmosphere through the third valve 86, and at this time, the tritium concentration in the air is finally measured by the third tritium monitor 88 (S290). ) The measurement of the tritium concentration thus measured again is provided to the control unit 95.

In addition, when the air passing through the dehumidifier 72 is measured by the second tritium detector 74 and the second H ₂ O monitor 76, the concentration of tritium and moisture in the air is greater than or equal to the target value, and the controller ( 95 blocks the discharge duct 82 with the flap door 78 and opens the recirculation duct 80.

The air passing through the dehumidifier 72 by blocking the discharge duct 82 is humidified again along the recirculation duct 80 which communicates with the inlet of the treatment duct 50 by opening the second valve 84. The dehumidification process is performed (S280).

If the air passing through the dehumidifier 72 does not continue to pass the target value for radioactive contamination or lower the target value, the decontamination treatment may be repeated by continuing the opening of the recirculation duct 80.

In addition, the treatment duct 50 has a singular structure, as shown in FIG. 4, but when the target value is strictly defined and the pollution degree is to be further lowered, the treatment duct 50 may be manufactured in a plural structure in parallel to further increase decontamination efficiency. You can also increase it.

In addition, by adjusting the flap door 78 appropriately, when the tritium concentration of the exhaust air exceeds the target value it can be adjusted to the desired degree.

For example, when the concentration of tritium in the air is twice the target value, the flap door 78 is adjusted so that more than 50% of the air is sent to the recirculation duct 80 (S300) and less than 50% of the air is discharged duct 82. If it is discharged through (S310), the tritium concentration of the air discharged may be less than the target value. At this time, the second valve 84 and the third valve 86 are opened by a signal from the control unit 95.

When the concentration of tritium in the discharged air exceeds the target value, if the flow air volume of the flap door 78 is adjusted in the same manner as described above, the concentration of tritium in the atmospheric discharged air can be discharged below the target value. have.

According to the present invention, when the air is discharged to the atmosphere using a treatment duct such that the air is contaminated with radioactive material in a nuclear power plant or a low pressure lower than atmospheric pressure, a humidification and dehumidification process is performed, thereby causing radioactive pollutants. In order to reduce the concentration of pollutants, it can be widely used in the nuclear industry.

1 is a view schematically showing an apparatus for removing radioactive pollutants in air according to an embodiment of the present invention.

FIG. 2 is a block diagram illustrating a method for removing radioactive contaminants in air using the apparatus shown in FIG. 1.

Figure 3 is a block diagram schematically showing an apparatus for removing radioactive pollutants in the air according to another embodiment of the present invention.

Figure 4 is a schematic view showing an apparatus for removing radioactive pollutants in the air according to another embodiment of the present invention.

FIG. 5 is a block diagram illustrating a method for removing radioactive contaminants in air using the apparatus shown in FIG. 4. FIG.

 FIG. 6 is a block diagram showing a method for controlling the opening and closing of the flap door shown in FIG. 4. FIG.

<Explanation of symbols for main parts of the drawings>

4: local humidifier 6: reactor building

8: Auxiliary Building 10: Local Humidifier

12: Water Storage Tank 16: Pump

18: Regional dehumidifier 20: Regional dehumidifier

22: dehumidification tank 26,96: outlet

28: radioactive waste storage tank 30: radioactive detector

50: treatment duct 56: first tritium detector

58: first H ₂ O monitor 60: flow meter

62: temperature controller 64: Pre Heater

66: water storage tank 68: humidifier

70: stirrer 72: dehumidifier

74: second tritium detector 76: second H ₂ O monitor

78: flap door 80: recirculation duct

82: exhaust duct 88,92: tritium monitor

90: dehumidification water storage tank 94: waste storage tank

Claims (15)

A local humidifier (4) installed to increase the moisture concentration in the air inside the nuclear power plant; A local dehumidifier 18 installed to collect and process tritium in air and moisture in contact with HTO by humidification of the local humidifier 4; and comprises tritium which is a radioactive material in a nuclear power plant. In the radioactive pollutant removal device in the air to reduce the concentration of tritium in the air polluted by       The local humidifier 4, the local humidifier 10 is installed in a large number of radioactive contaminated areas to spray the humidifying water in the reactor building (6) and auxiliary building (8), and the local humidifier (10) A water storage tank 12 connected to the pipe 14 so that water is supplied to the pipe 14, and a pump 16 installed to supply the water of the water storage tank 12 at a high pressure, The local dehumidifier 18, the dehumidification water is connected to the pipe 24 so that the dehumidification water is dehumidified by the local dehumidifier 20 and a plurality of local dehumidifier 20 is installed to dehumidify the inside of the contaminated area Storage tank 22, outlet 26 formed to be discharged when the dehumidifying water in the dehumidifying water storage tank 22 is not contaminated, and stored when the dehumidifying water in the dehumidifying water storage tank 22 is more than the reference value Radioactive waste storage tank characterized in that it comprises a liquid radioactive waste storage tank 28 is installed so as to detect the radioactive contamination concentration of the dehumidified water stored in the dehumidification water storage tank 22 Pollutant Removal Device. delete delete delete In the apparatus for removing radioactive pollutants in the air to reduce the tritium concentration in the process of releasing the air contaminated with tritium, which is a radioactive material in a nuclear power plant to the duct, Humidification means installed in the air discharge means to increase the moisture concentration; Dehumidifying means installed in the air discharge means to collect moisture in contact with tritium and HTO in the air by the humidification of the humidifying means; Control means for determining whether the removal target value for tritium in the air is exceeded through the control and sensing means of the humidifying means and the dehumidifying means; Radioactive pollutants in the air, characterized in that it comprises a duct opening and closing means for discharging the air to the atmosphere according to whether the target of the removal of tritium in the air passed through the humidifying means and the dehumidifying means as a signal of the control means. Removal device. The method of claim 5, The air discharge means is installed to communicate with the treatment duct 50 installed to discharge the polluted air in the nuclear power plant, and the start end of the treatment duct 50 after branching from the end of the treatment duct 50. Recirculation duct 80, and the discharge duct 82 is installed so that the air from which the radioactive pollutant is removed to the atmosphere from the end of the processing duct 50, the recycling duct 80 is branched. Apparatus for removing radioactive contaminants in air. The method of claim 5, wherein The humidifying means includes a humidifier 68 installed to be sprayed in the processing duct 50 in the flow direction, and a water storage tank 66 connected to the humidifier 68 to supply water. Apparatus for removing radioactive pollutants in the air. The method of claim 5, wherein The dehumidifying means, the dehumidifier 72 is installed in the air discharge means to collect the tritium in the air and the moisture in contact with the HTO by the humidification means, so that the dehumidified water dehumidified by the dehumidifier 72 is stored. The dehumidification water storage tank 90 to be connected, the tritium monitor 92 installed to detect the concentration of tritium in the dehumidification water in the dehumidification water storage tank 90, and the tritium concentration measured by the tritium monitor 92 Is a waste storage tank 94 that is installed to be classified and stored as a liquid radioactive waste when the target value is higher than, and the discharge port formed to be discharged to be classified as a general waste when the tritium concentration measured by the tritium monitor 92 is less than the target value (96) Apparatus for removing radioactive pollutants in the air, characterized in that it comprises a). The method of claim 5, wherein The control means, through the opening and closing of the first, second, third valves 54, 84, 86, heating and preheater 64 of the preheater 64, and control and sensing means such as the dehumidifier 72, And a control unit (95) for determining and controlling the removal target value for tritium. The method of claim 5, wherein The duct opening and closing means, the recirculation duct according to the signal of the control unit 95 determines whether the target value for the tritium concentration in the exhaust air in the nuclear power plant passed through the humidifier 68 and the dehumidifier 72 of the processing duct 50. And a flap door (78) installed to allow the air to be distributed to the duct side with the opening and closing (80) and the discharge duct (82). The method according to claim 5 or 6, The air discharge means, to remove the radioactive pollutants in the air, characterized in that the preheater 64, which is a heating means is further installed in the inlet which is the start end of the duct to heat the air flowing into the processing duct 50 Device. The method of claim 5, wherein Between the humidifying means and the dehumidifying means, a stirrer (70) to further improve the mixing of air and moisture is characterized in that the radioactive pollutant removal device in the air. The method according to claim 5 or 9, The sensing means may include a first tritium detector 56, a first H ₂ O monitor 58, a flow meter 60 installed to detect tritium concentration, moisture, and air content in the air before passing through the humidifier 68. After passing through the dehumidifier 72, the second tritium detector 74, the second H ₂ O monitor 76 and the discharge duct installed to detect the tritium concentration and water in the air flowing before and after the means; 82) The apparatus for removing radioactive pollutants in the air, characterized in that it comprises a tritium monitor (88) which is installed to detect the tritium concentration in the final discharged air through 82). In the method of removing radioactive pollutants in the air to reduce the concentration of tritium in the process of discharging air contaminated with tritium, which is a radioactive material in a nuclear power plant, to the duct, Humidifying the air in the air discharge means to the humidification means to increase the moisture concentration (S200), Dehumidifying the moisture in the air discharge means to the dehumidifying means to collect the moisture in contact with tritium and HTO in the air by the humidification of the humidifying means (S210), (S220) determining whether the control means exceeds the removal target value for tritium in the air through the control and sensing means of the humidifying means and the dehumidifying means; And discharging air to the atmosphere by means of a duct opening and closing means which is opened and closed according to whether a target value of tritium in the air passing through the humidifying means and the dehumidifying means has reached the signal of the control means (S230). How to remove heavy radioactive contaminants. The method of claim 14, If the tritium concentration in the air in the step (S230) is greater than or equal to the target value, the second valve 84 and the flap door 78 which is a duct opening and closing means is opened and the air is returned to the recirculation duct 80 to the flap door 78 by a certain amount. Distributing and recycling (S300), When the tritium concentration in the air in the step (S300) is less than the target value, a predetermined amount of air distributed to the discharge duct 82 side by the flap door 78 which is the third valve and the duct opening and closing means to be discharged to the atmosphere Method of removing radioactive contaminants in air, characterized in that it comprises a step (S310).

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