WO2018139208A1 - 原子力発電プラント - Google Patents

原子力発電プラント Download PDF

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Publication number
WO2018139208A1
WO2018139208A1 PCT/JP2018/000564 JP2018000564W WO2018139208A1 WO 2018139208 A1 WO2018139208 A1 WO 2018139208A1 JP 2018000564 W JP2018000564 W JP 2018000564W WO 2018139208 A1 WO2018139208 A1 WO 2018139208A1
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Prior art keywords
containment vessel
reactor containment
power plant
nuclear power
radioactive substance
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Ceased
Application number
PCT/JP2018/000564
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English (en)
French (fr)
Japanese (ja)
Inventor
宗平 福井
隆久 松崎
和明 木藤
佳彦 石井
政隆 日高
智彦 池側
克紀 浜田
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Hitachi GE Vernova Nuclear Energy Ltd
Original Assignee
Hitachi-GE Nuclear Energy Ltd
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Filing date
Publication date
Application filed by Hitachi-GE Nuclear Energy Ltd filed Critical Hitachi-GE Nuclear Energy Ltd
Priority to US16/479,989 priority Critical patent/US11515051B2/en
Publication of WO2018139208A1 publication Critical patent/WO2018139208A1/ja
Anticipated expiration legal-status Critical
Ceased legal-status Critical Current

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    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01D—SEPARATION
    • B01D53/00—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols
    • B01D53/22—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols by diffusion
    • B01D53/228—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols by diffusion characterised by specific membranes
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/004—Pressure suppression
    • G21C9/008—Pressure suppression by rupture-discs or -diaphragms
    • B—PERFORMING OPERATIONS; TRANSPORTING
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    • B01D53/22—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols by diffusion
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01D—SEPARATION
    • B01D53/00—Separation of gases or vapours; Recovering vapours of volatile solvents from gases; Chemical or biological purification of waste gases, e.g. engine exhaust gases, smoke, fumes, flue gases, aerosols
    • B01D53/34—Chemical or biological purification of waste gases
    • B01D53/74—General processes for purification of waste gases; Apparatus or devices specially adapted therefor
    • B01D53/86—Catalytic processes
    • B01D53/8671—Removing components of defined structure not provided for in B01D53/8603 - B01D53/8668
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    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
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    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01D—SEPARATION
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    • B01D71/02—Inorganic material
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    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
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    • B—PERFORMING OPERATIONS; TRANSPORTING
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    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
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    • G—PHYSICS
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    • G21C13/02—Details
    • G21C13/022—Ventilating arrangements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/004—Pressure suppression
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/02—Treating gases
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    • B01D2255/1021—Platinum
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    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
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    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
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    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the present invention relates to a nuclear power plant equipped with a reactor containment vent system.
  • a filter vent device for removing radioactive substances from a vent gas
  • a tank containing water vent gas is supplied into the water of the tank.
  • a metal filter and an iodine filter are provided at the outlet for discharging the vent gas from the pipe leading to the tank.
  • the vent gas is scrubbed by being released into the water in the tank to remove particulate radioactive materials.
  • particulate radioactive materials that could not be removed by scrubbing with the metal filter are further removed.
  • gaseous radioactive substances such as iodine are removed by chemical reaction and adsorption.
  • a pipe is connected to the reactor containment vessel, a radioactive substance separation device and a radioactive substance sealing device are provided outside the reactor containment vessel, and radioactive rare gases with poor reactivity such as xenon and krypton are provided from the vent gas.
  • a containment vessel vent system has also been proposed that separates and encloses it.
  • the reactor containment vessel vent system for the purpose of removing the radioactive noble gas needs to include a radioactive substance separation device and a radioactive substance sealing device as disclosed in Patent Document 2.
  • a large number of enclosures or large enclosures are required to separate all radioactive substances and enclose the separated radioactive substances for each element type or form of radioactive substance.
  • the radioactive material separation device is installed outside the reactor containment vessel, even if the separation membrane housed inside the radioactive material separation device can permeate the vapor, gas containing rare gas that does not permeate near the separation membrane is retained.
  • the above permeation performance cannot be maintained, the steam in the reactor containment vessel cannot be continuously discharged out of the system, and the pressure in the reactor containment vessel cannot be continuously reduced.
  • a return pipe into the containment vessel that constantly circulates the vented gas a device such as a pump that transports the vent gas, and a power source for using the device such as a pump. It is necessary to secure.
  • An object of the present invention is to provide a reactor containment vent system having a structure capable of continuously reducing the pressure of the reactor containment.
  • the present invention provides a reactor containment vessel containing a reactor pressure vessel, and a radioactive vessel that is disposed inside the reactor containment vessel and does not transmit radioactive noble gases but transmits steam.
  • the present invention even when a gas containing a radioactive substance flows out from the reactor pressure vessel into the containment vessel and the reactor containment vessel is pressurized, use an external power source. Therefore, it is possible to prevent pressurization of the reactor containment vessel and prevent leakage of radioactive materials to the surrounding environment.
  • FIG. 1 is a configuration diagram of a reactor containment vessel vent system according to Embodiment 1.
  • FIG. It is a block diagram of the reactor containment vessel vent system which concerns on Example 2.
  • FIG. It is a block diagram of the reactor containment vessel vent system which concerns on Example 3.
  • FIG. It is a block diagram of the reactor containment vessel vent system which concerns on Example 4.
  • FIG. It is a block diagram of the reactor containment vessel vent system which concerns on Example 5.
  • FIG. It is a block diagram of the reactor containment vessel vent system which concerns on Example 6.
  • FIG. It is a block diagram of the reactor containment vessel vent system which concerns on Example 7.
  • Example 8 FIG. It is a block diagram of the reactor containment vessel vent system which concerns on Example 9.
  • FIG. It is a block diagram of the reactor containment vessel vent system which concerns on Example 2.
  • FIG. 1 is a schematic diagram of a radioactive substance separation device according to Example 1.
  • FIG. 1 is a schematic diagram of a radioactive substance separation device according to Example 1.
  • FIG. 1 is a schematic diagram of a radioactive substance separation device according to Example 1.
  • FIG. 1 is a schematic diagram of a radioactive substance separation device according to Example 1.
  • One of the functions of the containment vessel provided in the nuclear power plant is that radioactive materials should be used in the event that the core placed in the reactor pressure vessel melts (hereinafter referred to as a severe accident). Is to be contained in the reactor containment vessel to prevent leakage to the outside. Even in the event of a severe accident, the accident will converge if sufficient water injection is performed thereafter and the reactor containment vessel is cooled. However, if steam generation continues and the reactor containment is not sufficiently cooled, the reactor containment may be pressurized. When the reactor containment vessel is pressurized, the gas in the reactor containment vessel may be released into the atmosphere in a controlled state, and the reactor containment vessel may be depressurized. This operation is called a vent operation. When performing this operation, in order to minimize exposure to the public in boiling water reactors, remove radioactive materials with pool water from the suppression pool, and then remove the gas in the reactor containment vessel (hereinafter referred to as vent gas). Release into the atmosphere.
  • vent gas When performing this operation, in order to minimize
  • the radioactive material is sufficiently removed by the pool water in the suppression pool, and then vent gas is released into the atmosphere.
  • the reactor is stored in the reactor as a system that further removes radioactive material from this vent gas. There is a container vent system.
  • FIG. 1 is a longitudinal sectional view showing a schematic configuration of a first embodiment of a reactor containment vessel and a reactor containment vessel vent system. The inside of the broken line in the figure is the reactor containment vessel vent system of the first embodiment.
  • the first embodiment of the containment vessel vent system reduces the pressure in the containment vessel in the event of a severe accident such as damage to the reactor pressure vessel, and removes radioactive materials as much as possible when the pressure is reduced. It is.
  • the reactor containment vent system shown in FIG. 1 is an example applied to an improved boiling water reactor and has the following system configuration.
  • a reactor pressure vessel 3 containing a reactor core 2 is installed in the reactor containment vessel 1.
  • the reactor pressure vessel 3 is connected to a main steam pipe 4 that sends steam generated in the reactor pressure vessel 3 to a turbine (not shown).
  • the inside of the reactor containment vessel 1 is divided into a dry well 6 and a wet well 7 by a diaphragm floor 5 made of reinforced concrete.
  • the wet well 7 refers to an area in which pool water is stored. This pool in the wet well 7 is called a suppression pool 8.
  • the dry well 6 and the wet well 7 are connected to each other by a vent pipe 9, and the vent pipe exhaust portion 9 a is opened below the water surface of the suppression pool 8 in the wet well 7.
  • a steam relief safety valve 10 is installed in the region of the dry well 6 in the reactor containment vessel 1.
  • the steam released through the steam relief safety valve 10 is finally discharged from the quencher 12 into the suppression pool 8 through the steam relief safety valve exhaust pipe 11 and condensed by the pool water of the suppression pool 8.
  • the volume of the steam is greatly reduced, and the pressure increase in the reactor containment vessel 1 can be suppressed.
  • the radioactive material is contained in the vapor, most of the radioactive material is removed by the scrubbing effect of the suppression pool 8 water.
  • the pressure in the reactor containment vessel 1 increases, even though this possibility is much less likely, if this spray does not work either.
  • the pressure increase in the reactor containment vessel 1 can be suppressed by releasing the gas in the reactor containment vessel 1 to the outside. This operation is called a vent operation.
  • a vent operation In a boiling water reactor, by performing this venting operation by releasing the gas in the wet well 7, it is possible to remove the radioactive material to the maximum with the water in the suppression pool 8 and then release the gas to the outside. it can.
  • the above operation removes most of the radioactive material, and the released gas from which the radioactive material has been removed is emitted from the exhaust tower 13.
  • the radioactive noble gas since the radioactive noble gas has poor reactivity, it cannot be removed by the vent system from the wet well 7. For this reason, the current vent operation must be performed after the radioactive noble gas has decayed, and therefore cannot be performed for a relatively short time after the reactor scram.
  • the radioactive substance separation device 14 is installed inside the reactor containment vessel 1 and the radioactive substance separation device 14 confines the radioactive noble gas, and the radioactive substance separation device.
  • the vent pipe 15 connected to the radioactive substance separation device 14 is located in the dry well 6 and the wet well 7 of the reactor containment vessel 1, and an isolation valve 16 is disposed in the vent pipe 15.
  • the isolation valve 16 may be an air operated valve, a burst valve, or a manually operable valve that can be opened and closed without using a power source.
  • the venting operation is usually performed by opening the isolation valve 16a on the wet well 7 side.
  • the vent pipe 15 finally exhausts gas from the exhaust tower 13 to the outside. It is also possible to remove the radioactive substance by the radioactive substance separation device 14 and open the vapor to the outside by opening the isolation valve 16b on the dry well 6 side.
  • the radioactive substance separation device 14 can remove radioactive noble gas at any position on the outside of the reactor containment vessel 1 or on the vent pipe, but by placing it inside the reactor containment vessel 1, the radioactive substance separation device 14 A pump for returning the radioactive noble gas removed by the separation membrane 14 to the reactor containment vessel 1 again or a sealed container for enclosing the radioactive noble gas is not required, and the structure is simpler. Furthermore, although the possibility is very low, even if the vent pipe 15 connected to the reactor containment vessel 1 is broken, the gas flowing through the vent pipe 15 is only a non-radioactive substance, so that the operator's exposure is not limited. It can be kept low.
  • the radioactive substance separation device 14 By placing the radioactive substance separation device 14 inside the containment vessel 1 in this way, (1) aerosol-like radioactive substance, (2) noble gas, (5) nitrogen is kept inside the containment vessel 1, Only (3) water vapor and (4) hydrogen can be discharged from the vent pipe 15 to the exhaust tower 13.
  • the radioactive substance separation device that is disposed inside the reactor containment vessel and does not transmit the radioactive noble gas and transmits the vapor, the radioactive substance is transferred from the reactor pressure vessel to the reactor containment vessel.
  • the contained gas flows out and the reactor containment vessel is pressurized, there is no need to use a pump to return the radioactive noble gas to the reactor containment vessel 1 again. For this reason, it is possible to prevent pressurization of the reactor containment vessel without using an external power source and to prevent the radioactive material from leaking into the surrounding environment.
  • the radioactive substance separation device 14 needs to transmit vapor.
  • hydrogen that may be generated when the core 2 is melted can pass therethrough.
  • Water vapor and hydrogen to be transmitted have a small molecular diameter of 0.3 nm or less, and radioactive noble gases (mainly krypton and xenon) that are not transmitted are considerably larger than that. Therefore, in order to selectively permeate vapor and hydrogen having a small molecular diameter, it is conceivable to use a membrane that can be separated by molecular sieving. In the case of a boiling water reactor, the gas in the reactor containment vessel 1 is replaced with nitrogen.
  • Membranes that can be separated by molecular sieves such as polymer membranes based on polyimide, ceramic membranes based on silicon nitride, graphene oxide membranes based on carbon, etc. Is desirable. These separation membranes are generally used in filters used for hydrogen purification. In addition, as long as the film does not transmit krypton or xenon but transmits hydrogen and water vapor, they may be used. For example, a separation membrane that allows hydrogen, water vapor, oxygen, and nitrogen to permeate may be used, such as a nitrogen separation membrane that transmits hydrogen, water vapor, and oxygen and does not permeate nitrogen.
  • FIG. 11 As the shape of the separation membrane 40, there are a plate shape as shown in FIG. 11, a tube shape and a hollow fiber shape as shown in FIGS.
  • the internal space of the radioactive substance separation device 14 is partitioned by a separation membrane 40 arranged parallel to the flow direction of the fluid flowing through the inside, and the fluid in the reactor containment vessel 1 is radioactive. It flows in from the bottom of the material separator 14 and flows to the top. Further, a part of the space partitioned by the separation membrane 40 is closed by the closing plate 43.
  • the internal space of the radioactive substance separation device 14 is partitioned by a tube-shaped separation membrane 40 arranged in parallel to the flow direction of the fluid flowing through the inside.
  • the fluid flows from the bottom of the tubular separation membrane 40 and flows upward.
  • aerosol-like radioactive material (2) radioactive noble gas, (6) nitrogen or (5) oxygen cannot permeate the separation membrane 40, so the reactor is stored from the top of the separation membrane 40. Returned to container 1.
  • (3) water vapor, (4) hydrogen or (5) oxygen permeates through the separation membrane 40 and is collected at one place and travels to the vent pipe 15.
  • a hollow fiber-shaped separation membrane 40 is arranged perpendicular to the flow direction of the fluid flowing inside, so that the fluid in the reactor containment vessel 1 Enters from the bottom of the radioactive material separator 14 and flows to the top.
  • aerosol-like radioactive substance (2) radioactive noble gas, (6) nitrogen or (5) oxygen cannot permeate the separation membrane 40. Returned to the furnace containment vessel 1.
  • water vapor, (4) hydrogen or (5) oxygen permeates the separation membrane 40 and enters the hollow fiber, is collected at one place, and heads to the vent pipe 15.
  • the separation membrane 40 has a structure in which the upstream space 41 and the downstream space 42 are completely partitioned, and the amount of the separation membrane 40 may be determined according to the amount of gas to be released.
  • the upstream space 41 is a space exposed to the gas in the reactor containment vessel 1, and only water vapor or hydrogen generated at the time of the accident can be released to the downstream space 42 through the separation membrane 40.
  • the gas in the upstream space 41 shown in FIGS. 11, 12, and 13 does not affect the separation performance of the separation membrane 40 regardless of whether the gas flows from the bottom to the top or from the top to the bottom.
  • the downstream space 42 is connected to the vent pipe 15 and is configured to release the released water vapor and hydrogen.
  • FIG. 2 is a longitudinal sectional view showing a schematic configuration of the second embodiment of the reactor containment vessel including the reactor containment vessel and the reactor containment vessel vent system.
  • the inside of the broken line in the figure is the reactor containment vessel vent system of the second embodiment.
  • the arrangement of the radioactive substance separation device 14 is the same as that of the first embodiment, and only the difference from the first embodiment will be described here.
  • Example 2 is an example in which a general filter vent device 17 is provided downstream of the radioactive material separation device 14 in case the separation membrane 40 inside the radioactive material separation device 14 is broken.
  • the vent pipe 15 is connected to the dry well 6 and the wet well 7 of the reactor containment vessel 1, and an isolation valve 16 is disposed in the vent pipe 15.
  • the vent pipe 15 is connected to the inlet pipe 18 of the filter vent device 17.
  • the distal end side of the inlet pipe 18 opens into the filter vent device 17.
  • a scrubbing pool water 19 is stored on the lower side in the filter vent device 17.
  • a metal mesh-like metal filter 20 and an iodine filter 21 are installed on the upper side of the filter vent device 17.
  • One end of the outlet pipe 22 of the filter vent device 17 is connected to the element filter 21.
  • the other end of the outlet pipe 22 passes through the shielding wall 23 and is led out of the shielding wall 23.
  • the gas is discharged from the exhaust tower 13 to the outside.
  • the filter vent device 17 is mainly used as a function of condensing the steam discharged from the reactor containment vessel 1 with the scrubbing pool water 19. .
  • the released gas that has entered the filter vent device 17 is scrubbed by the scrubbing pool water 19 so that most of the particulate radioactive material is mainly removed.
  • particulate radioactive material that could not be removed by scrubbing with the metal filter 20 can be removed, and gaseous radioactive material such as iodine can be removed with the iodine filter 21. This can reduce the risk of radioactive material being released into the environment and improve the reliability of the reactor containment vent system.
  • FIG. 3 is a longitudinal sectional view showing a schematic configuration of a third embodiment of a reactor containment vessel including a reactor containment vessel and a reactor containment vessel vent system.
  • the inside of the broken line in the figure is the reactor containment vessel vent system of the third embodiment.
  • the configuration of the filter vent device 17 is changed from the second embodiment, and only the difference will be described.
  • the filter vent device 17 generally includes wet and dry filter vent devices, and the wet vent device removes particles with the scrubbing pool water 19 in the container as in the second embodiment.
  • the filter vent device 17 according to the third embodiment is provided with a baffle plate 25 at the top, and a sand filter 24 for radioactive material removal is spread in the filter vent device 17 and the radioactive material is removed by the sand filter. It is.
  • This is a dry-type vent device, and it is not necessary to manage the water quality of the scrubbing pool water 19 as compared with the wet type, but it is necessary to heat this device in the event of an accident. Since the radioactive noble gas cannot be removed even with the filter vent device 17, the radioactive substance separation device 14 of the present invention is necessary, and the configuration thereof is the same as that of the second embodiment.
  • FIG. 4 is a longitudinal sectional view showing a schematic configuration of a fourth embodiment of a reactor containment vessel including a reactor containment vessel and a reactor containment vessel vent system.
  • the inside of the broken line in the figure is the reactor containment vent system of the fourth embodiment.
  • Example 4 it changes based on Example 2 and 3, and only the difference is demonstrated.
  • the radioactive substance separation device 14 is bypassed in the reactor containment vessel filter vent system of the second and third embodiments, and the bypass pipe 26 connected to the downstream portion of the radioactive substance separation device 14 is installed. Furthermore, by installing a rupture disc 27 that opens the valve when the pressure exceeds a certain level in the upstream portion of the bypass pipe 26, the separation membrane 40 inside the radioactive substance separation device 14 can be seen. When clogging occurs and the pressure in the reactor containment vessel 1 rises, the reactor containment vessel 1 can be depressurized by opening the rupture disk 27.
  • the rupture disk 27 may be a blast valve or another valve. Further, this function may be replaced by making the structure to be broken at a certain pressure or higher by the radioactive substance separation device 14 itself.
  • FIG. 5 is a longitudinal sectional view showing a schematic configuration of a fifth embodiment of a reactor containment vessel including a reactor containment vessel and a reactor containment vessel vent system.
  • the inside of the broken line in the figure is the reactor containment vessel vent system of the fifth embodiment.
  • the arrangement of the radioactive substance separation device 14 is the same as that of the first embodiment, and only the difference from the first embodiment will be described here.
  • the gas in the containment vessel 1 contains particulate radioactive material.
  • a particle collecting device 28 is installed at the entrance of the radioactive substance separating device 14 to collect particles as large as possible. With this mechanism, clogging due to adsorption of particles to the separation membrane 40 can be prevented, and deterioration of the separation membrane 40 due to exposure to strong radiation can be prevented.
  • a fibrous metal filter, hepa filter, adsorbent, or the like is effective for the particle collecting device 28, a fibrous metal filter, hepa filter, adsorbent, or the like is effective.
  • FIG. 6 is a longitudinal sectional view showing a schematic configuration of a sixth embodiment of a reactor containment vessel including a reactor containment vessel and a reactor containment vessel vent system.
  • the inside of the broken line in the figure is the reactor containment vessel vent system of the sixth embodiment.
  • the arrangement of the radioactive substance separation device 14 is the same as that of the first embodiment, and only the difference from the first embodiment will be described here.
  • the gas in the reactor containment vessel 1 contains gaseous iodine.
  • An iodine collection device 29 is installed at the inlet of the radioactive substance separation device 14 to collect as much gaseous iodine as possible. By this mechanism, the highly reactive gaseous iodine can be prevented from being deteriorated by physical adsorption and chemical adsorption on the separation membrane 40.
  • zeolite, silver silica gel, silver alumina, KI 3 adsorbed charcoal, etc. with silver impregnated are effective.
  • FIG. 7 is a longitudinal sectional view showing a schematic configuration of a seventh embodiment of a reactor containment vessel including a reactor containment vessel and a reactor containment vessel vent system.
  • the inside of the broken line in the figure is the reactor containment vessel vent system of the seventh embodiment.
  • the arrangement of the radioactive substance separation device 14 is the same as that in the first embodiment, and only the difference from the first embodiment will be described here.
  • the gas in the reactor containment vessel 1 is replaced with nitrogen, but at the time of the accident, 3% or less oxygen is present due to radiolysis of water.
  • a hydrogen recombination device 30 is installed at the entrance of the radioactive substance separation device 14, and hydrogen and oxygen in the reactor containment vessel 1 are combined to form water, thereby generating an exothermic reaction.
  • the gas heated by this exothermic reaction passes through the inside of the radioactive substance separation device 14, whereby the temperature of the separation membrane 40 can be kept high.
  • the higher the temperature of the separation membrane the higher the gas diffusion rate and the higher the separation rate. With this mechanism, the gas release rate by the separation membrane can be maintained high, and the reactor containment vessel 1 can be depressurized more quickly. Further, as a secondary effect of heating, an upward air flow is generated in the upstream space 41 of the separation membrane 40, so that impurities such as radioactive noble gas in the vicinity of the separation membrane 40 can be prevented.
  • the hydrogen recombination device 30 can directly increase the temperature of the separation membrane 40 by heating the gas as described above, and the radioactive material can be obtained by installing the hydrogen recombination device 30 on the outer periphery of the radioactive material separation device 14. It is also possible to heat the separation membrane 40 by raising the temperature of the separation device 14 itself.
  • the hydrogen recombination apparatus 30 is a catalyst in which palladium or platinum is impregnated on a support made of a mixed oxide such as cerium oxide and zirconium oxide. Alternatively, metal oxide catalysts containing metals such as lithium, sodium, magnesium, calcium, iron, nickel, copper, strontium, silver, and cerium are effective.
  • an igniter is installed in the reactor containment vessel 1 as a countermeasure for hydrogen treatment.
  • this igniter is installed at the inlet or the outer periphery of the radioactive substance separator 14, the reaction heat due to hydrogen recombination is obtained.
  • the separation membrane 40 can be heated using
  • FIG. 8 is a longitudinal sectional view showing a schematic configuration of an eighth embodiment of a reactor containment vessel including a reactor containment vessel and a reactor containment vessel vent system.
  • the inside of the broken line in the figure is the reactor containment vessel vent system of the eighth embodiment.
  • the arrangement configuration of the radioactive substance separation device 14 is the same as that of Example 1, and only the difference from Example 1 will be described here.
  • water vapor and hydrogen can be selectively separated and released to the vent pipe 15.
  • the concentration of water vapor or hydrogen in the upstream space 41 of the radioactive substance separator 14 is reduced and the concentration of nitrogen or oxygen as the main component of the reactor containment vessel 1 is reduced.
  • the difference in fluid density due to the increase in the nitrogen or oxygen concentration becomes a driving force that generates a descending airflow, so that the retention of impurities such as radioactive noble gas in the vicinity of the separation membrane 40 can be prevented.
  • FIG. 9 is a longitudinal sectional view showing a schematic configuration of a ninth embodiment of a reactor containment vessel including a reactor containment vessel and a reactor containment vessel vent system.
  • the inside of the broken line in the figure is the reactor containment vessel vent system of the ninth embodiment.
  • Example 9 is an example in which the reactor containment vessel filter vent system of Example 1 is applied to a pressurized water reactor.
  • the primary cooling water is pressurized by the pressurizer 32 in the reactor pressure vessel, circulated by the recirculation pump 34, and transported to the steam generator 33 (primary side).
  • the steam generator 33 heat is exchanged by the heat transfer pipe, and heat is transported from the primary side to the secondary side to generate steam, and the steam flows through the main steam pipe 4.
  • the pressurized water reactor does not have the wet well 7 and the suppression pool 8 for suppressing the pressure rise in the reactor containment vessel 1, removal of radioactive materials by scrubbing with the suppression pool 8 cannot be expected. Therefore, by opening the isolation valve 16 of the dry well 6, the radioactive substance is removed by the radioactive substance separator 14 and the vapor is discharged to the outside.
  • Example 1 The same as Example 1 except that there is no vent from the wet well 7 side.
  • a wet filter vent device 17, a dry filter vent device 17, a rupture disk 27, a particle collection device 28, an iodine collection device 29, a hydrogen recombination device 30, and a chimney 31 are used. It doesn't matter.
  • FIG. 10 is a longitudinal sectional view showing a schematic configuration of a tenth embodiment of a reactor containment vessel including a reactor containment vessel and a reactor containment vessel vent system.
  • the inside of the broken line in the figure is the reactor containment vessel vent system of the tenth embodiment.
  • Example 10 has a secondary reactor containment vessel 36 containing a primary reactor containment vessel 35 as a reactor containment vessel.
  • the secondary reactor containment vessel 36 communicates with the dry well 6 and the wet well 7 inside the primary reactor containment vessel 35 through the vent pipe 15 and the isolation valve 16.
  • the gas vented from the primary reactor containment vessel 35 flows into the vent pipe 15 via the radioactive substance separation device 14 installed in the primary reactor containment vessel 35 and is released into the secondary reactor containment vessel 36.
  • the radioactive substance separation device 14 can prevent the radioactive substance from being transferred to the secondary reactor containment vessel 36.
  • the separation membrane 40 inside the radioactive substance separation device 14 is broken and the radioactive substance is released through the vent pipe 15 by any chance.
  • the radioactive substance can be confined in the secondary reactor containment vessel 36.
  • efficient hydrogen treatment can be performed by installing the hydrogen recombination apparatus 30 in the vicinity of the outlet of the vent pipe 15 having a high hydrogen concentration.
  • Other configurations are the same as those in the first embodiment.
  • the radioactive substance separation device 14 may be provided inside the secondary reactor containment vessel 36, and the radioactive substance separation device 14 may be configured such that the exhaust tower 13 is installed outside the secondary reactor containment vessel 36 via the vent pipe 15.
  • the filter vent device 17 according to the second and third embodiments may be provided inside the secondary reactor containment vessel 36, and the outlet pipe 22 may be communicated with the inside of the secondary reactor containment vessel 36 instead of the exhaust tower 13.
  • the filter vent device 17 may be installed outside the secondary reactor containment vessel 36 and vented from the secondary reactor containment vessel 36 through the filter vent device 17 to the outside.
  • SYMBOLS 1 ... Reactor containment vessel, 2 ... Core, 3 ... Reactor pressure vessel, 4 ... Main steam pipe, 5 ... Diaphragm floor, 6 ... Dry well, 7 ... Wet well, 7a ... Wet well gas phase part, 8 ... Suppression Pool, 9 ... Vent pipe, 9a ... Vent pipe exhaust part, 10 ... Steam relief safety valve, 11 ... Steam relief safety valve exhaust pipe, 12 ... Quencher, 13 ... Exhaust tower, 14 ... Radioactive substance separator, 15 ... Vent pipe, 16 ... Isolation valve, 16a ... Wet well side isolation valve, 16b ... Dry well side isolation valve, 17 ... Filter vent device, 18 ...
  • Inlet piping 19 ... Pool water for scrubbing, 20 ... Metal filter, 21 ... Iodine filter, 22 ... Exit piping, 23 ... Shielding wall, 24 ... Sand filter for removing radioactive substances, 25 ... Baffle plate, 26 ... Bypass pipe, 27 ... Rupture disk, 28 ... Particle collection 29 ... Iodine collector, 30 ... Hydrogen recombination device, 31 ... Chimney, 32 ... Pressurizer, 33 ... Steam generator, 34 ... Recirculation pump, 35 ... Primary reactor containment vessel, 36 ... Secondary Primary containment vessel, 40 ... separation membrane, 41 ... upstream space, 42 ... downstream space, 43 ... closing plate

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