KR101494074B1 - Complex Apparatus Removable for Airborne Radioactive Materials - Google Patents

Abstract

The present invention relates to a device for removing radioactive material in a complex type air conditioner, and more particularly, to a device for removing radioactive material in a real time automatically according to the amount and concentration of the radioactive material. (Co, Ni, etc.), iodine radioactive material [(oxo (I) (I)], or radioactive iodine released from the primary system of a real-time nuclear power plant in proportion to the concentration and amount of radioactive material contained in air generated in the system And the like), a radioactive material such as argon (Ar), krypton (Kr), radon (Rn), xenon (Xe) .

Description

TECHNICAL FIELD [0001] The present invention relates to a moving type complex air-

The present invention relates to a device for removing radioactive material in a complex type air conditioner, and more particularly, to a device for removing radioactive material in a real time automatically according to the amount and concentration of the radioactive material. (Co, Ni, etc.), iodine radioactive material [(oxo (I) (I)], or radioactive iodine released from the primary system of a real-time nuclear power plant in proportion to the concentration and amount of radioactive material contained in air generated in the system And the like), a radioactive material such as argon (Ar), krypton (Kr), radon (Rn), xenon (Xe) .

Nuclear power plants conduct scheduled preventive maintenance routinely to ensure safe operation of nuclear reactors, increase reliability, improve utilization and ensure continuous output operation.

During the planned preventive maintenance period, replacement of the fuel assemblies reaching the end of the design combustion period loaded in the reactor improves the output and efficiency, and tests and tests various devices.

During the planned preventive maintenance period, maintenance workers work directly into the radioactive hazard facilities and risk exposure to radioactive materials is very high. Particularly, the radioactive material generated during the decomposition and inspection of the primary system, such as the reactor, is composed of particulate radioactive materials (cobalt (Co), nickel, etc.), iodine radioactive substances There are radiation sources such as argon (Ar), krypton (Kr), radon (Rn), xenon (Xe), etc.) To minimize in-vitro exposure and maintain a clean and reliable nuclear power plant, which is a nuclear power plant operation philosophy, it is necessary to be able to effectively remove radioactive materials from the air generated in the primary system of the power plant.

Nuclear power plants are operating radioactive air purification facilities [114] to purify polluted air from these radioactive materials.

However, the above-mentioned low-volume purification facility is operated as a purification facility when the contaminated air is distributed in the entire reactor containment building (total capacity: 58,050 m 3), but the purification facility required to recover the reactor containment building to a clean state before the pollution It takes a considerable amount of time (about 30 days), and workers who work on site during the period of purification have been exposed to internal and external exposures.

And there is little effect in continuously removing high-level radioactive contaminants present in the water chamber, such as the steam generator 110 or the pressurizer 111 installed in the containment building.

Accordingly, in order to solve the limitations of the conventional facilities and techniques, the present invention has been developed in view of the above problems, and it is an object of the present invention to provide a particulate radioactive material (cobalt (Co), nickel, etc.) It has been possible to research and develop a device capable of effectively removing radioactive materials such as radioactive materials (oxo (I), etc.) and gaseous radioactive materials (argon (Ar), krypton (Kr), xenon (Xe)

Korean Patent Registration No. 10-863680 discloses a technical structure of 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 However, it differs from the complex airborne radioactive material removal device configured to automatically remove the radioactive material in real time according to the amount and concentration of the radioactive material.

Japanese Unexamined Patent Publication (Kokai) No. 1994-347593 discloses a related art in which radioactive gaseous waste is transferred from a main condenser to an hydrogen recombination container through an air extractor to recombine hydrogen gas and reduce the volume of the waste gas, It differs from the complex airborne radioactive material removal device configured to cool and dehumidify by transferring the gas to the dehumidifying cooler and to remove the radioactive material automatically in real time according to the amount and concentration of the air containing the radioactive material.

The problem to be solved by the present invention is to prevent worker exposure due to high-level radioactive material pollution sources generated in main facilities of nuclear power plant (pressurizer, steam generator, and reactor head lifting) It is urgent to develop mobile radioactive material removal equipment suitable for the characteristics of a nuclear power plant, and it is necessary to develop the particulate radioactive material (cobalt (Co), nickel, etc.) released from the main facilities of the primary system. There is provided a mobile complex type airborne radioactive material removal apparatus capable of effectively removing radioactive materials such as [(oxo (I) and the like], gaseous radioactive materials (such as argon, krypton, xenon etc.) .

Another problem to be solved by the apparatus for removing radioactive material in air according to the present invention is that it is small in size, easy to move and install, and can be conveniently used in a narrow space. Therefore, And the radioactive material generated in the head can be measured and removed in real time automatically according to concentration and amount.

Another problem to be solved by the present invention is that each processing unit has a structure that can be easily combined and separated and can be closed by itself, and after each radioactive material is collected, each sealed unit is divided into a plurality of And is stored in a closed room for a longer time than the half-life, thereby effectively removing radioactive materials.

Another problem to be solved by the present invention is to allow the adsorbent to be reused after the storage period has elapsed after the adsorbent is subjected to a thermal desorption / regeneration process.

In order to achieve the above object, in order to achieve the above-mentioned object, in order to achieve the above-mentioned object, in the process of preventing radioactive material in the air during the planned preventive maintenance period of the nuclear power plant, The present invention also provides an apparatus for removing radioactive substances in a mobile complex type air which can be easily applied according to the types and characteristics of the radioactive materials generated in the above three steps.

The present invention is also directed to a method for removing radioactive material in a mobile complex air system, which is applied step by step according to the present invention, in which the radioactive contamination generated in the primary system of a nuclear power plant (where nuclear fuel radioactive materials are generated) Air is planned to remove 99.98% or more of the radioactive material contained in the air generated in the primary system during the three phases of the process during the preventive maintenance period.

In order to solve the above problem, the present invention provides a method for removing radioactive materials, comprising the steps of: (a) removing radioactive materials from a gas phase of about 10 m 3 (argon, krypton, radon Rn), Xenon (Xe), etc.) is prevented from diffusing into the containment building. It is a "Mobile Complex Type Air Radioactive Material Removal Device" at the entrance when the pressurizer manway (M / W) (Ar) (Ar), which is generated inside the pressurizer by connecting a movable type air intake pipe for the radioactive material removal device of movable complex type to the low volume system of the containment building located at the upper side of about 30m, , Krypton (Kr), radon (Rn), xenon (Xe), etc.) are automatically removed in real time according to the concentration and amount, and the second step is to remove particles and oxo from the steam generator (24 inches of bellows hose diameter for shrinkage) is connected to the inlet of the steam generator discharge valve, and then a movable composite airborne radioactive material removal device is connected to the containment building low volume system located at the top of about 90 m. (Cobalt (Co), nickel (Ni), and iodine (iodine) emitted from the inside of the steam generator valve at the same time as the steam generator valve is opened. Step 3 is to prevent diffusion of gaseous radioactive material (argon, krypton (Kr), radon (Rn), xenon (Xe), etc.) trapped in the bottom before withdrawing the reactor head (3/8 inch shrinkable bellows hose 3/8 inch) to the reactor head valve valve and then to the containment building low volume system located approximately 180m above the mobile complex air stream Removal of material Substantially automatic removal of gaseous radioactive materials (Ar, Krypton, Radon, Xen, etc.) trapped in the bottom of the reactor head by connecting the downstream air intake pipe The present invention provides an apparatus for removing radioactive materials in a mobile complex type air.

The apparatus for removing radioactive materials in a moving complex type air according to the present invention is small in size, easy to move and install, and can be conveniently used in a narrow space. Therefore, There is an advantageous effect that the substance can be measured and removed according to concentration and amount in real time automatically.

As a further effect of the present invention, each treatment section has a structure that can be easily combined and separated, and can be closed by itself. After collecting the radioactive material, each sealed section is longer than the half- The radioactive material can be effectively removed by keeping it in a closed room for a period of time.

Another advantage of the present invention is that since the adsorbent can be reused after the storage period of the adsorbent, the economical efficiency is excellent.

1 is a perspective view showing an improved primary system radioactive material purification system of a nuclear power plant.
FIG. 2 is an apparatus for removing radioactive materials in the mobile complex air in the present invention shown in FIG.
FIG. 3 shows the first and second flow rate differential pressure regulating devices, the radiation measuring device and the voice converting device according to the present invention shown in FIG. 2.

Hereinafter, the present invention will be described in detail.

The first step for removing the radioactive material from the mobile complex type airborne radioactive material removal apparatus according to the present invention is to remove the gas radioactive material [Ar, Krypton (M / W) of the pressurized manway (M / W) is prevented from diffusing into the containment building, The air intake pipe (shape: shrinkable bellows hose diameter: 8 inches) installed at the front of the radioactive material removal device is connected to the containment building low volume system located at about 30 m above the radioactive material removal device, (Argon (Ar), krypton (Kr), radon (Rn), xenon (Xe), etc.) generated in the pressurizer by connecting the air suction pipe installed at the rear end of the pressurizer Depending is configured to real-time automatically removed via a take-off bellows hose (see 119 in FIG. 1).

The second step according to the present invention is a procedure for removing the particles and oxo generated in the steam generator. After connecting an air suction pipe (shape: 24 inch diameter of a bellows hose for shrinkage) to the inlet of the steam generator discharge valve, (Cobalt (Co), Nickel, etc.) and iodine generated from the inside of the steam generator valve while simultaneously connecting the air intake pipe installed at the rear end of the "mobile complex type airborne radioactive material removal device" to the low- [(Oxo (I), etc.] The radioactive material is designed to be automatically removed in real time according to the concentration and amount (see 120 in FIG. 1).

The third step according to the present invention is a method in which a gas radioactive material (argon, krypton (Kr), radon (Rn), xenon (Xe), etc.) trapped at the bottom of the reactor head As a part of blocking the spreading, the air intake pipe (shape: 3/8 inches for shrinking bellows) installed at the front of the mobile complex type airborne radioactive material removal device is connected to the reactor head valve valve, (Ar), krypton (Kr), radon (Rn), and radon (Rn) trapped in the lower part of the reactor head by connecting the air intake pipe installed at the rear end of the "mobile type complex air- Xenon (Xe), etc.) according to their concentration and amount. A specific embodiment of the present invention will be described.

<Examples>

Technical constructions according to the present invention will be described in detail with reference to the drawings. 1 shows an improved primary system radioactive material purification system 100 of a nuclear power plant.

FIG. 2 is a block diagram of a first flow rate and second flow rate differential pressure regulator 218 designed in accordance with the present invention, a bellows hose blower 219, a radioactive concentration monitor 223, a first flow rate meter 216, A second flow velocity meter 217, and the like, according to an embodiment of the present invention.

The arrows indicated at 120 in FIG. 2 indicate the direction of air flow.

Referring to FIGS. 1 and 2, an apparatus for removing radioactive materials in a mobile complex air according to the present invention is designed to remove radioactive (non-radioactive) radioactive substances in a primary system of a nuclear power plant Remove the material.

In the first step of each process, the gaseous radioactive material generated from the PZR manway is removed by a drawing bellows hose (119 in Fig. 1).

In order to carry out this process, the moving type complex airborne radioactive material removing apparatus according to the present invention is installed with a draw-out bellows hose (119 in FIG. 1).

In FIG. 1, reference numeral 114 denotes an apparatus installed in a conventional system for purifying air by a primary system radioactive material purification system of a nuclear power plant, and a rear end of a movable complex type air- As shown in Fig.

The method for removing radioactive material using a moving type complex air-based radioactive material removing device is composed of three purification operation modes, a first operation mode for removing gaseous radiation materials on the pressurizer side, a second operation mode for removing steam from the steam generator side To remove particulate and oxo materials, and a third mode of operation [116] is to remove the reactor side gaseous radiation material.

Since the first operation mode and the third operation mode are for removing the same material, a mobile complex type air-borne radioactive material removal apparatus having the same configuration is employed.

The first operation mode of the device for removing the movable complex type airborne radioactive material removal apparatus is a bellows fixing flange 211 (shape: bellows hose diameter of 8 inches for shrinkage) connected to the PZR manway, And the bellows fixing flange is fastened and fixed to the presser manway by a plastic bolt for fixing the bellows hose.

The water removing unit 225 is provided with a pressurizer internal radioactive material concentration detector 224 and a differential pressure gauge 222 for measuring the difference between the flow rate at the entrance side of the containment building low purge system and the pressure at the outlet of the pressurizer manway exit Is provided at one side of the inside of the water removing unit 225. A differential pressure flow rate regulator 218 is fixedly installed at the left end of the moving type complex airborne radioactive material removal apparatus.

A flow rate integration measuring device 217 for integrating the flow rate of gaseous radioactive material generated inside the pressurizer is installed at the end of the apparatus. And a winding induction motor 215 for artificially extracting the gas containing the radioactive material in the pressurizer to the outside is connected to the water removing unit 225 through a bellows.

In the first operation mode, a withdrawing bellows hose (length of about 30 m) (119 of FIG. 1) is connected and installed in order to transfer the radioactivity in the right end (flow meter) .

The first operation mode is a facility required to remove the gaseous radioactive material from the first systematic radioactive material. The main components include a radioactive material concentration meter 224, a differential pressure meter 222, a first flow rate meter 216, A flow rate measuring device 217, a flow rate measuring device 217, a winding type induction motor 215 for transmitting the radioactive material in the gas generated inside the presser to the inlet side of the purge system of the containment building, As shown in FIG. 2, and they are fixedly installed on one side of the movable type complex air-based radioactive material removal device.

The radioactive material concentration sensor real-time measures the concentration of gaseous radioactive material generated in the primary system pressurizer from a low concentration to a high concentration value (unit: μCi / cc).

The measured value of the concentration of the radioactive material is transmitted to the rotational speed regulating device in order to interlock with the rotational speed regulating device of the wound-wire-type induction motor 215. The radioactivity value at the high concentration is the rotational speed of the wound-type induction motor (range: 1,800 to 3,600 RPM) is operated in a low rotation range, and the low concentration radioactivity value is configured to be operated in a high rotation range.

The flow rate and the flow rate measured at the inlet side (220 in FIG. 2) of the containment building low volumetric purge system and at the outlet side (116 in FIG. 2) of the pressurizer manway are transferred to the rotational speed regulating device of the induction motor 215, Is used to control the rotational speed of the motor (215).

The differential pressure flow rate regulator 218 interlocked with the differential pressure gage 222 for measuring the differential pressure between the inlet-side flow rate of the containment building low-volume purge system and the flow rate of the pressurizer manway outlet-side flow rate controls the flow rate of the gas radioactive material at the outlet of the pressurizer 111 And containment building low volumetric purge system (114) As a control device to keep the outlet velocity of the radionuclide at the inlet side the same, the velocity of the gaseous radioactive material released is lowered at the end compared with the inlet side outlet velocity. Thereby preventing flow deterioration.

The air treated in the particulate removing unit 213 is conveyed through the draw-out bellows hose 119 (see FIG. 1). In this case, inert gas such as argon (Ar), krypton ), Radon (Rn), xenon (Xe), and the like are removed.

The particulate eliminator 213 may be a HEPA filter and / or a charcoal filter or a structure having equivalent functions so long as it can process the gases.

Generally, since the inert gas such as argon (Ar), krypton (Kr), radon (Rn), and xenon (Xe) can freely pass through the filter, it is difficult to remove such radioactive inert gas by the filter-type purifier.

The adsorption of Kr and Xe as a function of temperature (data from Eshaya and kalinowski [1961]) of inert gas (Ar, Kr, Rn, Xe) It has been reported that the inert gas can be removed by physical adsorption when brought into contact, but its demonstration device has not been developed. The present invention was invented as an empirical apparatus so as to more efficiently perform degassing by low-speed physical adsorption.

In the second step 117 of the process according to the present invention, the mobile complex type air which removes the particles and the iodine radioactive material from the water storage room through the low volume system of the containment building by discharging the particles and iodine radioactive material generated in the steam generator water chamber And a radioactive substance remover 117.

In the second step process 117, the operation mode of the movable complex air-based radioactive material removal device (first operation mode: gas removal device, second operation mode: particle and oxo removal device, third operation mode: The second operation mode 120 is used to remove particles and oxo radioactive material generated from the steam generator manway.

The particulate and oxo radioactive material removal device 120 includes a customized ring-connected shear air intake pipe 211 (shape: bellows hose diameter 24 inches for shrinkage), an internal steam particle generator inner particle and an oxo radioactive material concentration sensor 223, A first flow rate measuring device 216, a second flow rate measuring device 220, particles and oxo radioactive material flow rate measuring device 217 generated in the steam generator, A hose single deformation field (221), a coiled induction motor (215) for artificially extracting a gas containing radioactive material contained in the steam generator internal particles and oxo (215), a low- A bellows hose 120 for shrinking (about 90 m in length) to be transferred to the purge system 114 and a containment building low-volume purge system 114 are connected to the inlet side flow amount and the steam generator manway outlet side oil A differential pressure gauge 222 for measuring a differential pressure by using the differential pressure, and a differential pressure regulator 218 for interlocking with the differential pressure gauge.

The particles and the oxo radioactive material removal device 120 corresponding to the second operation mode 120 are still another embodiment of the moving type complex airborne radioactive material removal device according to the present invention, The configuration is also fixed to one side of the movable complex type airborne radioactive material removal device as shown in FIG. 2, like the configuration described in the first operation mode.

The unidirectional grating window 221 is arranged at a distance of 3 to 7 m in the bellows hose (about 90 m) connected from the steam generator to the containment building low volume system 114, Low-volume system).

The unidirectional diaphragm window 221 is provided to prevent the leakage of the gas in the reverse direction when a failure occurs in the wire-wound induction motor 215 or the power supply system is lost due to other causes.

The particulate removing unit 213 serves to remove particulates and other impurity gases contained in the air from which moisture and oxides have been removed through the water removing unit 225 and the oxide gas removing unit.

Specifically, the particulate removing unit 213 is made of an activated carbon non-woven fabric 135, which is an adsorbent 214 for removing oxide gas and removing oxides.

The air introduced into the particulate removing unit 213 passes through the activated carbon nonwoven fabric 214, and other particulate matter and other impurities are removed.

In the embodiment of the present invention, the air flow is configured to sequentially pass the water removal unit 225, the oxide gas removal unit, and the particulate removal unit 213 in this order.

The materials of the water removing unit 225, the oxide gas removing unit, the particulate removing unit 213, the first connecting pipe 119, the second connecting pipe 116 and the third connecting pipe 117 are made of a bellows hose for shrinking It is preferable to use a product that has passed the pressure resistance test with a water pressure of 6 kg / cm 2.

The third stage corresponds to the third operation mode and the gas radioactive material [argon (Ar), krypton (Kr), radon (Rn), xenon (Xe), etc.) trapped in the lower part before the withdrawal of the reactor head (3/8 inches of shrinkable bellows hose) to the reactor head valve valve before the mobile complex type airborne radioactive material removal device to prevent diffusion into the containment building. (Ar), krypton (Kr), radon (Rn), xenon (Xe), etc., which are trapped in the lower part of the reactor head by connecting the air intake pipe at the rear end of the movable complex type air- ] Is automatically removed in real time according to the concentration and amount.

Each of the figures shown in the lower part of FIG. 2 and the upper part of FIG. 2 shows a front view (lower part) and a plan view (upper part) of the water removing part 225, the winding induction motor 215 and the flowmeter.

The configuration of the mobile type complex air-borne radioactive material removal apparatus in the third step has the same configuration as the first step.

The movable complex type airborne radioactive substance removal apparatus 200 according to the present invention will be described with reference to the apparatus 200 for removing radioactive substances in the mobile complex type as shown in FIG. 1, but the present invention is not limited thereto It will be understood by those skilled in the art that various changes in form and details may be made therein without departing from the spirit and scope of the invention as defined by the appended claims.

In addition, terms and words used in the present specification and claims should not be construed to be limited to ordinary or dictionary terms, and the inventor should properly define the concept of the term to describe its own invention in the best way. The present invention should be construed in accordance with the meaning and concept consistent with the technical idea of the present invention.

The present invention relates to a device for removing radioactive material in a complex type air conditioner, and more particularly, to a device for removing radioactive material in a real time automatically according to the amount and concentration of the radioactive material. (Co, Ni, etc.), iodine radioactive material [(oxo (I) (I)], or radioactive iodine released from the primary system of a real-time nuclear power plant in proportion to the concentration and amount of radioactive material contained in air generated in the system ) And a radioactive material such as a gaseous radioactive material (such as argon (Ar), krypton (Kr), radon (Rn), xenon (Xe) It is very likely to be industrially applicable by efficiently removing the radioactive material at a high removal rate.

100; Improved primary system radioactive material purification system
110; Steam Generator
111; Pressurizer (PZR)
112; nuclear pile
113; Reactor water tank
114; Containment building low-volume purge system
115; Reactor coolant pump
116; Bellows for extracting radioactive materials from nuclear reactors
117; Steam Generator Bellows for extracting radioactive material
118; Reactor coolant piping
119; Bellows hose for drawing
200; Combined airborne radioactive material removal device
210; Steam generator (pressurizer)
211; Flange for fixing bellows hose
212; Plastic Bolt for fixing bellows hose
213; Particle removal
214; Charcoal filter
215; Winding induction motor
216; The first flow rate meter
217; Flow Accumulation Measuring Apparatus
218; The first and second flow velocity differential pressure regulators
219; Bellows hose blower
220; The second flow rate meter
221; Bellows hose single lattice
222; The first flow rate and the second flow rate differential pressure meter
223; Measurement of particles and oxo radiation and audio equipment
224; Gas radiation measurement and sound equipment
225; Moisture removal
226; Dehumidifier

Claims (7)

A complex type airborne radioactive material removal apparatus for extracting a gas containing a radioactive material inside a pressurizer (111) to the outside, comprising:
A bellows hose fixing flange 211 for connecting and fixing the bellows hose 119 to the pressurizer 111 manway;
A radioactive material concentration sensor 224 installed at one side of the bellows fixing hose fixing flange for measuring the concentration of the radioactive material contained in the gas introduced from the inside of the pressurizer;
A differential pressure gauge (222) installed at one side of the bellows hose to measure a pressure difference due to the flow rate measurement at the outlet of the pressurizer and the inlet side of the containment building purge system;
A differential pressure regulating device (218) configured to interlock with the differential pressure gauge;
A gaseous radioactive material flow rate accumulation measuring device 217 generated in the pressurizer to accumulate the flow rate of gaseous radioactive material flowing from the pressurizer;
A water removing unit 225 installed at the rear of the bellows to remove water contained in the gas;
A particulate removing unit 213 installed at the rear end of the water removal unit to remove the oxide gas and the oxo gas contained in the gas;
A unidirectional lattice window 221 installed inside the bellows hose to remove particles and oxo radioactive material and configured to allow a flowing fluid to flow in a predetermined direction; And
A wire wound type induction motor installed at the next stage of the particle removing unit 213 for extracting a gas containing radioactive material to the outside,
When the radioactive material concentration value measured by the radioactive material concentration sensor 224 is a high concentration radioactive value, the rotation speed of the wire-wound induction motor 215 controls the rotation speed of the wire-wound induction motor to be lower Wherein the rotating speed of the wound induction motor is operated at a higher rotational speed than at a higher radioactive value. delete delete delete The method according to claim 1,
Wherein the particulate removing unit (213) installed in the moving type complex airborne radioactive substance removing apparatus is manufactured and installed as an activated carbon nonwoven fabric as an adsorbent for removing oxide gas and removing oxides. The method according to claim 1,
The differential pressure regulator 218 in conjunction with the differential pressure gauge in the moving complex type airborne radioactive material removal apparatus detects the flow rate of the gas radioactive material at the outlet of the pressurizer manway 111 and the outlet velocity of the inlet radioactive material Wherein the flow rate is controlled so as to be maintained at the same value to prevent a fluid flow deterioration phenomenon in which the discharge rate at the end is lowered. The method according to claim 1,
The moving type complex air-based radioactive material removal apparatus is characterized in that the front end of the air intake pipe is connected to the reactor head valve valve to prevent the gaseous radioactive material trapped in the lower part from being diffused into the containment structure before the withdrawal of the reactor head, Wherein the air intake pipe is connected to the volume system at a rear end thereof to remove gaseous radioactive material trapped under the reactor head.

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