JP6016381B2 - Primary containment vessel maintenance equipment and primary containment vessel maintenance method - Google Patents

Description

  The present invention relates to a containment vessel maintenance facility and a containment vessel maintenance method for ensuring the safety of a containment vessel during a severe accident.

  Conventionally, in a nuclear power plant, as countermeasures assuming a severe accident in which the core melts and flows out of the reactor pressure vessel, for example, in Patent Document 1, a capture unit that captures the melt flowing out of the reactor pressure vessel, and a refrigerant A melt cooling structure is shown which has a plurality of tube portions that are provided in a refrigerant storage portion in which is stored and through which the melt flows in via a supplementary portion. This melt cooling structure prevents the melted out melt from accumulating in a mountain shape by dispersing the melt into a plurality of portions and depositing them in the cylinder portion. Moreover, the cooling efficiency of the melt flowing out from the reactor is improved by increasing the contact area between the subdivided melt flowing into the tube section via the tube section and the refrigerant in the refrigerant storage section.

  Further, for example, in Patent Document 2, a steam vent pipe that connects an upper dry well and a pressure suppression pool, and an interior of the lower dry well at a position lower than the water level of the pressure suppression pool in a normal state and the pressure suppression pool are connected. A cooling water channel pipe and a temperature actuated valve function provided in the cooling water channel pipe in the lower dry well, which is normally closed and opened when the temperature in the lower dry well becomes higher than a predetermined temperature; A nuclear power plant having a check valve function that allows a flow from the pressure suppression pool side to the lower dry well side and blocks a flow from the lower dry well side to the pressure suppression pool side is shown. In this nuclear power plant, water can be injected into the lower dry well using the pressure suppression pool as a water source in the event of an emergency of the nuclear reactor, and the pressure suppression function of the pressure suppression pool is not impaired.

  Further, for example, Patent Document 3 discloses a system for drafting countermeasures such as an evacuation plan and an evacuation training plan in the event of an accident in a nuclear power plant. This system performs accident analysis of the corresponding accident based on the cause accident, obtains source term information on the radioactivity released in the cause accident, and nuclear power based on weather forecast information around the nuclear power plant. Based on the airflow distribution analysis means for analyzing the 3D airflow distribution around the plant, the source term information and the 3D airflow distribution, the 3D atmospheric diffusion state around the nuclear power system is analyzed for the radioactivity emitted in the corresponding event. Diffusion state analysis means that calculates the dose distribution of radiation emitted from this radioactivity based on the three-dimensional atmospheric diffusion state, and the exposure dose around the nuclear power plant is predicted based on the dose distribution Exposure dose prediction means.

JP 2011-174897 A JP 2011-133372 A JP 2003-215246 A

  When the melt is submerged and cooled, water vapor is generated in the reactor containment vessel due to the decay heat of the melt. Then, when the pressure inside the reactor containment vessel rises due to the filling of water vapor and exceeds the pressure resistance of the reactor containment vessel, the reactor containment vessel may be destroyed. In order to avoid such a situation, conventionally, as described in Patent Document 1 and Patent Document 2, a device for improving the cooling efficiency and the pressure suppression function has been made.

  On the other hand, when the internal pressure of the containment vessel rises and exceeds the pressure resistance of the containment vessel, it is necessary to release water vapor to the outside of the containment vessel in order to lower the internal pressure. An exhaust mechanism having a filter for removing the above will be provided.

  Such an exhaust mechanism is designed to have the best filter performance capable of removing radioactive substances, but it is desirable to determine the timing of exhaust and the amount of exhaust by the exhaust mechanism in consideration of further safety. .

  The present invention solves the above-described problems, and provides a containment vessel maintenance facility and a containment vessel maintenance method capable of determining an exhaust timing and an exhaust amount by an exhaust mechanism in consideration of safety. For the purpose.

  In order to achieve the above object, a containment vessel maintenance facility according to the present invention is a reactor containment vessel maintenance facility provided in a reactor containment vessel that houses a reactor pressure vessel containing a core in an airtight state. An exhaust pipe withdrawn to the outside of the reactor containment vessel; an exhaust mechanism having a filter connected to the exhaust pipe to remove radioactive substances from water vapor generated inside the reactor containment vessel; and the reactor containment vessel And a control unit for setting an exhaust timing and an exhaust amount by the exhaust mechanism based on pressure information inside the reactor, weather information around the reactor containment vessel, and location information.

  According to this reactor containment maintenance equipment, the exhaust timing and the amount of exhaust are set by the exhaust mechanism according to the weather conditions and location conditions around the reactor containment while monitoring the pressure inside the reactor containment. Thus, the exhaust timing and the exhaust amount by the exhaust mechanism can be determined in consideration of the safety of the reactor containment vessel and the area around the reactor containment vessel.

  In order to achieve the above-mentioned object, the reactor containment vessel maintenance method of the present invention is drawn out of the reactor containment vessel in the reactor containment vessel containing the reactor pressure vessel containing the core in an airtight state. A reactor containment vessel maintenance method using an exhaust pipe and an exhaust mechanism connected to the exhaust pipe and having a filter that removes radioactive substances from water vapor generated inside the reactor containment vessel, the reactor containment vessel Obtaining the pressure information inside, the weather information and the location information around the reactor containment vessel, and then the exhaust timing and the displacement by the exhaust mechanism based on the pressure information, the weather information and the location information And a step of setting.

  According to this reactor containment maintenance method, while monitoring the pressure inside the reactor containment, the exhaust timing and the amount of exhaust are set by the exhaust mechanism according to the weather conditions and location conditions around the reactor containment Thus, the exhaust timing and the exhaust amount by the exhaust mechanism can be determined in consideration of the safety of the reactor containment vessel and the area around the reactor containment vessel.

  According to the present invention, the exhaust timing and the exhaust amount by the exhaust mechanism can be determined in consideration of safety.

FIG. 1 is a schematic configuration diagram of an example of a nuclear power plant. FIG. 2 is a configuration diagram of a reactor containment maintenance facility according to an embodiment of the present invention. FIG. 3 is a flowchart showing the operation of the reactor containment maintenance facility according to the embodiment of the present invention.

  Embodiments according to the present invention will be described below in detail with reference to the drawings. In addition, this invention is not limited by this embodiment. In addition, constituent elements in the following embodiments include those that can be easily replaced by those skilled in the art or those that are substantially the same.

  FIG. 1 is a schematic configuration diagram of an example of a nuclear power plant. The nuclear power plant shown in FIG. 1 is a pressurized water reactor (PWR: Pressurized Water Reactor). In this nuclear power plant, in a containment vessel 100, a reactor pressure vessel 101, a pressurizer 102, a steam generator 103 and a primary cooling water pump 104 are sequentially connected by a primary cooling water pipe 105 to circulate primary cooling water. The route is configured.

  The reactor pressure vessel 101 stores therein a plurality of fuel assemblies 101a, which are cores, in a sealed state, and a vessel body 101b and a vessel lid 101c mounted on the upper portion thereof so that the fuel assemblies 101a can be inserted and removed. It is comprised by. The container lid 101c is provided so as to be openable and closable with respect to the container main body 101b. The container main body 101b has a cylindrical shape with an upper opening and a lower hemispherical shape that is closed, and an inlet-side nozzle 101d and an outlet-side nozzle 101e that supply and discharge light water as primary cooling water are provided at the upper part. It has been. The outlet side nozzle 101e is connected to the primary cooling water pipe 105 so as to communicate with the inlet side water chamber 103a of the steam generator 103. The inlet side nozzle 101d is connected to the primary cooling water pipe 105 so as to communicate with the outlet side water chamber 103b of the steam generator 103.

  The steam generator 103 is provided with an inlet-side water chamber 103a and an outlet-side water chamber 103b partitioned by a partition plate 103c in a lower part formed in a hemispherical shape. The inlet side water chamber 103a and the outlet side water chamber 103b are separated from the upper side of the steam generator 103 by a tube plate 103d provided on the ceiling portion. On the upper side of the steam generator 103, an inverted U-shaped heat transfer tube 103e is provided. The end portion of the heat transfer tube 103e is supported by the tube plate 103d so as to connect the inlet side water chamber 103a and the outlet side water chamber 103b. The inlet-side water chamber 103a is connected to the inlet-side primary cooling water pipe 105, and the outlet-side water chamber 103b is connected to the outlet-side primary cooling water pipe 105. In addition, the steam generator 103 is connected to the upper side upper end partitioned by the tube plate 103d, the outlet side secondary cooling water pipe 106a, and the upper side part is connected to the inlet side secondary cooling water pipe 106b. Has been.

  Further, in the nuclear power plant, the steam generator 103 is connected to the steam turbine 107 via the secondary cooling water pipes 106a and 106b outside the reactor containment vessel 100, and the circulation path of the secondary cooling water is configured.

  The steam turbine 107 includes a high-pressure turbine 108 and a low-pressure turbine 109, and a generator 110 is connected to the steam turbine 107. In addition, the high-pressure turbine 108 and the low-pressure turbine 109 are connected to a moisture separation heater 111 that is branched from the secondary cooling water pipe 106a. The low pressure turbine 109 is connected to the condenser 112. The condenser 112 is connected to the secondary cooling water pipe 106b. The secondary cooling water pipe 106b is connected to the steam generator 103 as described above, and reaches from the condenser 112 to the steam generator 103, and the condensate pump 113, the low-pressure feed water heater 114, the deaerator 115, and the main feed water pump. 116, a high-pressure feed water heater 117 and a main feed valve 118 are provided.

  Therefore, in the nuclear power plant, the primary cooling water is heated in the reactor pressure vessel 101 to become high temperature and high pressure, and is pressurized by the pressurizer 102 to maintain the pressure constant, while the steam is passed through the primary cooling water pipe 105. It is supplied to the generator 103. In the steam generator 103, heat exchange between the primary cooling water and the secondary cooling water is performed, whereby the secondary cooling water evaporates and becomes steam. The cooled primary cooling water after heat exchange is recovered to the primary cooling water pump 104 side via the primary cooling water pipe 105 and returned to the reactor pressure vessel 101. On the other hand, the secondary cooling water converted into steam by heat exchange is supplied to the steam turbine 107. In connection with the steam turbine 107, the moisture separator / heater 111 removes moisture from the exhaust from the high-pressure turbine 108, further heats it to an overheated state, and then sends it to the low-pressure turbine 109. The steam turbine 107 is driven by the steam of the secondary cooling water, and the power is transmitted to the generator 110 to generate power. Steam used for driving the turbine is discharged to the condenser 112. The condenser 112 exchanges heat between the cooling water (for example, seawater) taken by the pump 112b through the intake pipe 112a and the steam discharged from the low-pressure turbine 109, and condenses the steam to produce a low-pressure saturated liquid. Return to. The cooling water used for heat exchange is discharged from the drain pipe 112c. Further, the condensed saturated liquid becomes secondary cooling water, and is sent out of the condenser 112 by the condensate pump 113 through the secondary cooling water pipe 106b. Further, the secondary cooling water passing through the secondary cooling water pipe 106b is heated by the low-pressure feed water heater 114, for example, by the low-pressure steam extracted from the low-pressure turbine 109, and dissolved oxygen and non-condensed gas (ammonia gas) in the deaerator 115. After the impurities such as) are removed, the water is fed by the main feed pump 116 and heated by the high-pressure steam extracted from the high-pressure turbine 108 by the high-pressure feed water heater 117 and then returned to the steam generator 103. Here, a system for supplying secondary cooling water to the steam generator 103 is referred to as a main water supply system. In the main water supply system, the main water supply pump 116, the main water supply valve 118, and the like are controlled in order to maintain the water level of the secondary cooling water of the steam generator 103.

  FIG. 2 is a configuration diagram of a nuclear reactor containment maintenance facility that is an application example of the shielding structure and the shielding method according to the present embodiment. As shown in FIG. 2, a reactor cavity 10 is provided inside the reactor containment vessel 100 so as to surround the lower part of the vessel main body 101 b of the reactor pressure vessel 101. The reactor cavity 10 captures the melt and cools the melt by injecting cooling water during a severe accident in which the core melts and flows out of the reactor pressure vessel 101.

  The reactor containment maintenance facility includes an exhaust mechanism 2. The exhaust mechanism 2 includes an exhaust pipe 21 drawn out of the reactor containment vessel 100 to the outside of the reactor containment vessel 100 and a filter 22 connected to the exhaust pipe 21 outside the reactor containment vessel 100. Have.

  The exhaust pipe 21 is provided with an exhaust valve 21a. The exhaust valve 21a is composed of, for example, an electric valve, and opens or closes exhaust in the exhaust pipe 21. The filter 22 is a cylinder whose top and bottom are closed and has a sealed structure.

  The filter 22 is provided with a nozzle pipe 22a connected to the exhaust pipe 21 below the inside thereof. For example, the nozzle pipe 22 a extends downward in the filter 22 while being connected to the exhaust pipe 21, and is provided to be branched into a plurality of horizontal radial directions at the bottom inside the filter 22. An exhaust nozzle 22b is provided at each branched tip. The exhaust nozzle 22 b is immersed in the adsorbing liquid L injected into the filter 22. The adsorbing liquid L is water, and an adsorbent may be added. The filter 22 is provided with a steam / water separator 22c above the inside thereof. The steam / water separator 22c is a parallel arrangement of a plurality of corrugated plates, and is provided separately from the adsorbed liquid L. The filter 22 is provided with an exhaust pipe 22d leading to the outside at the upper part thereof.

  The exhaust mechanism 2 discharges water vapor generated inside the reactor containment vessel 100 when the melt is cooled by the cooling water in the reactor cavity 10 during a severe accident, and the exhaust valve 21a is opened. Thus, the water vapor generated inside the reactor containment vessel 100 is passed through the adsorbing liquid L by the filter 22 in the process of discharging the water vapor generated inside the reactor containment vessel 100 to the outside of the reactor containment vessel 100 through the exhaust pipe 21 and the exhaust pipe 22d. To remove radioactive material from the water. Further, the exhaust mechanism 2 stops the discharge of water vapor to the outside of the reactor containment vessel 100 by closing the exhaust valve 21a.

  In the present embodiment, the reactor containment vessel 100 is provided with a pressure gauge 4 for detecting the pressure inside the reactor containment vessel 100.

  Further, the reactor containment vessel maintenance facility of this embodiment has a control unit 6. The control unit 6 is configured as a microprocessor centered on a CPU (Central Processing Unit). In addition to the CPU, a ROM (Read Only Memory) that stores a processing program and a RAM that temporarily stores data. (Random Access Memory) and a computer system including a storage device.

  The control unit 6 inputs pressure information iA detected by the pressure gauge 4. Moreover, the control part 6 inputs the weather information iB. The meteorological information iB may be meteorological information provided by the Japan Meteorological Agency, or meteorological information provided by the National Oceanic and Atmospheric Administration. The weather information database 7 may be a database, and the weather information iB may be input from the weather information database 7. The weather information iB mainly includes wind direction, rainfall, snowfall, wind speed, temperature, and the like. Further, the control unit 6 inputs the location information iC from the location information database 8. This location information database 8 is a database of the surrounding topography, texture, etc., centering on the nuclear power plant. And the control part 6 controls opening / closing of the exhaust valve 21a by the exhaust command iD according to the pressure information iA, the weather information iB, and the location information iC. Further, the control unit 6 notifies the start or stop of exhaust by an exhaust command iD corresponding to the pressure information iA, the weather information iB, and the location information iC. This notification is performed by display on a monitor, a buzzer, a lamp, or the like. In this case, the operator operates the exhaust valve 21a based on the notification.

  The exhaust command iD output by the control unit 6 includes an exhaust timing that is an opening timing of the exhaust valve 21a and an exhaust amount that is an opening time of the exhaust valve 21a. In order to set the exhaust timing and the exhaust amount, the control unit 6 has an exhaust timing determination unit 61 and an exhaust amount determination unit 62.

  The exhaust timing determination unit 61 predicts a rising tendency of the pressure inside the reactor containment vessel 100 based on the input of the pressure information iA, and determines the exhaust valve from the time until the upper limit pressure that the reactor containment vessel 100 can withstand in design. The opening timing of 21a is determined.

  Further, the exhaust timing determination unit 61 receives the weather information iB and the location information iC, and determines the exhaust valve according to the location where the exhausted water vapor reaches based on the current wind direction, the predicted future wind direction, the topography, and the geography. The opening timing of 21a is determined.

  Further, the exhaust timing judgment unit 61 inputs the weather information iB, and the exhaust valve 21a according to the fall of the water vapor exhausted based on the current rainfall or the predicted future rainfall (rainfall amount) and snowfall (snowfall amount). To determine the opening timing.

  Further, the exhaust timing determination unit 61 determines the opening timing of the exhaust valve 21a according to the expansion state of the exhausted water vapor based on the current wind speed and the predicted future wind speed by inputting the weather information iB.

  Further, the exhaust timing judgment unit 61 sets the opening timing of the exhaust valve 21a according to the expansion state of the exhausted water vapor based on the current temperature or the predicted future temperature (airflow due to the temperature) by inputting the weather information iB. to decide.

  The exhaust timing determination unit 61 can set a weight on the above-described determination. For example, first, when the pressure in the reactor containment vessel 100 exceeds the upper limit pressure, the reactor containment vessel 100 may be destroyed, so the opening timing of the exhaust valve 21a is determined. For example, secondly, the opening timing of the exhaust valve 21a is determined on the basis of the wind direction, the topography, and the ground in consideration of the location where the exhausted water vapor reaches. For example, thirdly, based on rain (rainfall) and snowfall (snow accumulation), the opening timing of the exhaust valve 21a is determined in consideration of the fall of the water vapor exhausted. For example, fourthly, based on the wind speed, the opening timing of the exhaust valve 21a is determined in consideration of the expanded state of the exhausted water vapor. For example, fifthly, based on the temperature, the opening timing of the exhaust valve 21a is determined in consideration of the expansion state of the exhausted water vapor.

  The displacement determining unit 62 predicts a rising tendency of the pressure inside the reactor containment vessel 100 based on the input of the pressure information iA, and stores the reactor within a range that reaches the upper limit pressure that the reactor containment vessel 100 can withstand in design. The opening time of the exhaust valve 21a that can reduce the pressure inside the container 100 to a predetermined pressure is determined.

  In addition, the exhaust amount determination unit 62 receives the weather information iB and the location information iC, and determines the exhaust valve according to the location where the exhausted water vapor reaches based on the current wind direction, the predicted future wind direction, and the topography or geography. The opening time of 21a is determined.

  In addition, the exhaust amount determination unit 62 receives the weather information iB and inputs the exhaust valve 21a according to the fall of the water vapor exhausted based on the current or predicted future rainfall (rainfall amount) and snowfall (snow accumulation amount). Determine the opening time.

  Further, the exhaust amount determination unit 62 determines the opening time of the exhaust valve 21a according to the expansion state of the exhausted water vapor based on the current wind speed and the predicted future wind speed by inputting the weather information iB.

  Further, the exhaust amount determination unit 62 sets the opening time of the exhaust valve 21a according to the expansion state of the exhausted water vapor based on the current temperature or the predicted future temperature (airflow due to the temperature) by inputting the weather information iB. to decide.

  Note that the exhaust amount determination unit 62 can set a weight on the above-described determination. For example, the weighting is set in ascending order of the exhaust amount.

  FIG. 3 is a flowchart showing a reactor containment maintenance method that is an operation of the reactor containment maintenance facility according to the present embodiment.

  FIG. 3 shows a case where a severe accident occurs. During severe accidents, the reactor cavity 10 is filled with cooling water to cool the trapped melt. At this time, water vapor is generated in the reactor containment vessel 100 due to the decay heat of the melt. For this reason, the pressure inside the reactor containment vessel 100 increases.

  Therefore, the control unit 6 acquires the pressure information iA, the weather information iB, and the location information iC, and based on the pressure information iA, the weather information iB, and the location information iC, the exhaust timing and the exhaust amount (opening time of the exhaust valve 21a). Judging.

  Specifically, the control unit 6 acquires the pressure information iA (step S1), and from the increasing pressure inside the reactor containment vessel 100 to the upper limit pressure that the reactor containment vessel 100 can withstand in design. A time is predicted to determine the exhaust timing α1 of the exhaust valve 21a, and an exhaust amount (opening time of the exhaust valve 21a) β1 that can reduce the pressure inside the containment vessel 100 to a predetermined pressure is determined (step S2). ).

  At the same time, the control unit 6 acquires the weather information iB and the location information iC (step S3), and determines the exhaust timing α2 and the exhaust amount (exhaust time of the exhaust valve 21a) β2 suitable for exhaust (step S4).

  Next, when the exhaust timing α1 is closer to the exhaust timing α2, that is, when the exhaust timing α2 exceeds the range of time until the reactor containment vessel 100 reaches the upper limit pressure that can be withstanding by design (step S5: Yes). The control unit 6 selects the exhaust timing α1 determined from the pressure information iA (step S6).

  Next, when the exhaust amount β1 is smaller than the exhaust amount β2 (step S7: Yes), the exhaust amount β1 determined by the pressure information iA is selected (step S8).

  Then, the selected exhaust timing α1 and exhaust amount β1 are set, and an exhaust command iD is output (step S9).

  In step S7, when the exhaust amount β1 is larger than the exhaust amount β2 (step S7: No), the control unit 6 selects the exhaust amount β2 determined from the weather information iB and the location information iC (step S10). .

  Then, the control unit 6 sets the selected exhaust timing α1 and exhaust amount β2, and outputs an exhaust command iD (step S11).

  On the other hand, in step S5, when the exhaust timing α1 is farther than the exhaust timing α2, that is, when the exhaust timing α2 is within the time range until reaching the upper limit pressure that the reactor containment vessel 100 can withstand in design (step S5). S5: No), the control unit 6 selects the exhaust time α2 determined from the weather information iB and the location information iC (step S12).

  Next, when the exhaust amount β1 is smaller than the exhaust amount β2 (step S13: Yes), the control unit 6 selects the exhaust amount β1 determined from the pressure information iA (step S14).

  Then, the control unit 6 sets the selected exhaust timing α2 and exhaust amount β1, and outputs an exhaust command iD (step S15).

  In step S13, when the exhaust amount β1 is larger than the exhaust amount β2 (step S13: No), the control unit 6 selects the exhaust amount β2 determined from the weather information iB and the location information iC (step S16). .

  Then, the control unit 6 sets the selected exhaust timing α2 and exhaust amount β2, and outputs an exhaust command iD (step S17).

  In step S9, step S11, step S15, and step S17, when the operator operates the exhaust valve 21a, the control unit 6 sets the exhaust timing and the exhaust amount, and notifies the exhaust command iD.

  As described above, the containment vessel maintenance facility according to the present embodiment provides for the containment vessel maintenance provided in the reactor containment vessel 100 that accommodates the reactor pressure vessel 101 that stores the core (the fuel assembly 101a) in an airtight state. Exhaust mechanism 2 having an exhaust pipe 21 drawn out of the reactor containment vessel 100 and a filter 22 connected to the exhaust pipe 21 to remove radioactive substances from water vapor generated inside the reactor containment vessel 100. And a control unit 6 that sets an exhaust timing and an exhaust amount by the exhaust mechanism 2 based on pressure information iA inside the reactor containment vessel 100, weather information iB around the containment vessel 100, and location information iC. .

  According to the reactor containment maintenance facility, the exhaust timing and the amount of exhaust by the exhaust mechanism 2 are monitored according to the weather condition and the location situation around the reactor containment vessel 100 while monitoring the pressure inside the reactor containment vessel 100. By setting the above, it becomes possible to determine the exhaust timing and the exhaust amount by the exhaust mechanism 2 in consideration of the safety of the reactor containment vessel 100 and the area around the reactor containment vessel 100.

  Moreover, the reactor containment vessel maintenance method of the present embodiment is the reactor containment vessel 100 that houses the reactor pressure vessel 101 that houses the core (fuel assembly 101a) in an airtight state. A reactor containment vessel maintenance method using an exhaust mechanism 21 having an exhaust pipe 21 that is drawn out and a filter 22 that is connected to the exhaust pipe 21 and removes radioactive substances from water vapor generated inside the reactor containment vessel 100. , The step of obtaining the pressure information iA inside the reactor containment vessel 100, the weather information iB and the location information iC around the reactor containment vessel 100, and then the pressure information iA, the weather information iB and the location information iC And a step of setting an exhaust timing and an exhaust amount by the exhaust mechanism 2.

  According to this reactor containment vessel maintenance method, while monitoring the internal pressure of the reactor containment vessel 100, the exhaust timing and the amount of exhaust by the exhaust mechanism 2 according to the weather conditions and location conditions around the reactor containment vessel 100. By setting the above, it becomes possible to determine the exhaust timing and the exhaust amount by the exhaust mechanism 2 in consideration of the safety of the reactor containment vessel 100 and the area around the reactor containment vessel 100.

  In the above-described embodiment, the application object of the reactor containment maintenance facility has been described as a nuclear power plant that is a pressurized water reactor. However, in a nuclear power plant that is a boiling water reactor (BWR), a nuclear reactor is used. It is also possible to apply a containment maintenance facility.

2 Exhaust Mechanism 21 Exhaust Piping 21a Exhaust Valve 22 Filter 22a Nozzle Piping 22b Exhaust Nozzle 22c Air / Water Separator 22d Exhaust Pipe 4 Pressure Gauge 6 Control Unit 61 Exhaust Timing Judgment Unit 62 Exhaust Amount Judgment Unit 7 Meteorological Information Database 8 Location Information Database 10 Reactor cavity 100 Reactor containment vessel 101 Reactor pressure vessel iA Pressure information iB Weather information iC Location information iD Exhaust command L Adsorbed liquid

Claims (2)

A reactor containment vessel maintenance facility provided in a reactor containment vessel that houses a reactor pressure vessel containing a core in an airtight state,
An exhaust pipe that is drawn out of the reactor containment vessel, and an exhaust mechanism that has a filter that is connected to the exhaust pipe and removes radioactive substances from water vapor generated inside the reactor containment vessel;
Based on the pressure information inside the reactor containment vessel, the weather information around the reactor containment vessel and the location information, the exhaust timing and the exhaust amount by the exhaust mechanism are set, and the exhaust timing according to the pressure information and the Comparing the weather information and the exhaust time according to the location information, and comparing the exhaust amount according to the pressure information and the exhaust amount according to the weather information and the location information, the exhaust time and the exhaust time A control unit for setting a weight on the quantity;
A reactor containment vessel maintenance facility characterized by comprising: In a reactor containment vessel that contains a reactor pressure vessel containing a reactor core in an airtight state, an exhaust pipe drawn out of the reactor containment vessel, and connected to the exhaust pipe and generated inside the reactor containment vessel A containment vessel maintenance method using an exhaust mechanism having a filter that removes radioactive substances from water vapor,
Obtaining pressure information inside the containment vessel, meteorological information and location information around the containment vessel, and
Next, an exhaust timing and an exhaust amount by the exhaust mechanism are set based on the pressure information, the weather information, and the location information, and the exhaust timing according to the pressure information, the weather information, and the location information are set. and compared with the exhaust timing, and by comparing the emissions and in accordance with the exhaust amount of the weather information and the location information corresponding to the pressure information, sets the weighting to the exhaust timing and the exhaust amount step,
Containment method for containment of nuclear reactor containment.

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