WO2001016962A1 - Equipement de securite pour reacteur - Google Patents

Equipement de securite pour reacteur Download PDF

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Publication number
WO2001016962A1
WO2001016962A1 PCT/JP1999/004639 JP9904639W WO0116962A1 WO 2001016962 A1 WO2001016962 A1 WO 2001016962A1 JP 9904639 W JP9904639 W JP 9904639W WO 0116962 A1 WO0116962 A1 WO 0116962A1
Authority
WO
WIPO (PCT)
Prior art keywords
water
pressure vessel
reactor
housing
reactor pressure
Prior art date
Application number
PCT/JP1999/004639
Other languages
English (en)
Japanese (ja)
Inventor
Kohei Hisamochi
Shingo Oda
Koji Hashimoto
Kenichi Sato
Original Assignee
Hitachi, Ltd.
Hitachi Engineering Co., Ltd.
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Hitachi, Ltd., Hitachi Engineering Co., Ltd. filed Critical Hitachi, Ltd.
Priority to PCT/JP1999/004639 priority Critical patent/WO2001016962A1/fr
Publication of WO2001016962A1 publication Critical patent/WO2001016962A1/fr

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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • 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
    • G21C9/016—Core catchers
    • 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
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the present invention relates to a nuclear plant, and more particularly to a reactor safety facility for cooling a reactor vessel that has been overheated.
  • the hot core melt moves down and falls into the lower plenum in the reactor pressure vessel. Then, the heat of the core melt that has fallen into the lower plenum penetrates the lower mirror portion and lower mirror portion of the reactor pressure vessel, and the temperature of the housing mounted on the reactor pressure vessel rises. If the temperature exceeds the damage limit temperature of the reactor pressure vessel, the lower part of the reactor pressure vessel will be damaged and the core melt will be discharged into the reactor containment vessel, the building containing the reactor pressure vessel. .
  • the reactor pressure vessel is efficiently cooled from the inside to prevent damage to the lower part of the reactor pressure vessel due to maturation of the core melt This will prevent it.
  • the cooling means from the inside is lost or the cooling capacity is insufficient, cooling will be performed from the outside of the reactor pressure vessel.
  • FIG. 10 An example of cooling from the outside of the reactor pressure vessel is disclosed in Japanese Patent Application Laid-Open No. 10-300883.
  • the contents are as follows. That is, in a cooling device for a reactor vessel incorporating a reactor core, a water spraying unit for spraying cooling water to an outer wall surface at a bottom of the reactor vessel, and a temperature detection for detecting a temperature at a bottom of the reactor vessel. And the bottom temperature detected by this temperature detector And a control means for causing the water spraying means to start water spraying when the temperature exceeds a set temperature.
  • the control means automatically causes the watering means to start watering, and the cooling water flows to the outer wall surface at the bottom of the reactor vessel.
  • the cooling effect of the water spray suppresses the temperature rise at the bottom of the reactor vessel.
  • the cooling device further includes a bottom cover that covers an outer wall surface at a bottom of the reactor vessel at an interval, and the watering unit includes an outer wall surface at a bottom of the reactor vessel and the bottom cover. And watering is performed in the gap between the two.
  • the cooling water sprinkled by the water sprinkling means is surely spread over the entire outer wall at the bottom of the reactor vessel. The entire bottom can be effectively cooled.
  • the emergency core cooling system did not operate, and other water injection equipment into the reactor pressure vessel could not be used. If it falls into the lower plenum, a means to cool the reactor pressure vessel from outside is being considered.
  • the steam loses its escape route and stays as it is.
  • the sealed space must be in a state of high temperature and high pressure, Since it cannot be injected into the space, it cannot be cooled continuously.
  • An object of the present invention is to provide a reactor safety facility capable of reliably achieving cooling from the outside of a reactor pressure vessel.
  • the first invention is characterized in that a water storage area penetrating a structure protruding from the reactor pressure vessel is formed below an outer side of the reactor pressure vessel, and a water injection facility for injecting water into the water storage area and inner and outer sides of the water storage area.
  • Reactor safety equipment equipped with a communication port for communication.
  • the structure protruding from the reactor pressure vessel transfers the heat of the reactor pressure vessel to the outside and guides it to the outside.
  • the heat induced to the outside is cooled and cooled by the water injected from the water injection equipment, which comes into contact with the housing immediately after the water injection or the water injected into the water storage area.
  • the injected water accumulates in the water storage area, spreads right below the center of the reactor pressure vessel, and reliably removes heat from the structure directly below it. Injection that has become hot due to the pressure, heat, and cooling function in the water storage area escapes from the communication port and receives new water injection into the water storage area to obtain a continuous cooling effect.
  • a water injection area configured to penetrate a structure penetrating between the inside and outside of the reactor pressure vessel below the reactor pressure vessel, and a water injection facility for injecting water into the water storage area, Reactor safety equipment equipped with a communication port that communicates inside and outside the water storage area.
  • the structure penetrating between the inside and outside of the reactor pressure vessel is The part that protrudes inside the reactor pressure vessel receives the surrounding heat and transfers it to the outside to guide it to the outside.
  • the heat induced to the outside is cooled by water cooling when water injected from the water injection equipment comes into contact with the housing immediately after water injection or comes into contact with water injected in the water storage area.
  • the heat in deep parts inside the reactor pressure vessel is well guided to the outside, and it is suitable for cooling the deep parts.
  • the injected water accumulates in the water storage area, reaches right below the center of the reactor pressure vessel, and reliably removes heat from the structure immediately below. Injection that has become hot due to the pressure, heat and cooling function in the water storage area escapes from the communication port and receives new water injection into the water storage area to obtain a continuous cooling effect.
  • a water storage area is formed below and outside the reactor pressure vessel by penetrating a control rod drive mechanism housing and a Z or a nuclear instrumentation housing provided in the reactor pressure vessel.
  • This is a reactor safety facility comprising: a water injection facility for injecting water into a water storage area; and a communication port provided between the bottom of the water storage area and a location higher than the bottom of the water storage area and communicating with the inside and outside of the water storage area.
  • the control rod drive mechanism housing and / or the nuclear instrumentation housing provided in the reactor pressure vessel is a structure penetrating between the inside and the outside of the reactor pressure vessel.
  • the portion of the housing that protrudes inside the reactor pressure vessel receives ambient heat and transfers it to the portion of the housing that protrudes outside the reactor pressure vessel, and the heat induced by the heat transfer action to the outside
  • the water injected from the water injection equipment comes into contact with the housing immediately after the water injection or the water injected into the water storage area, and is cooled and cooled.
  • the water in the water storage area is stored at a depth that does not exceed the position of the communication port, and the water spreads below the center of the reactor pressure vessel. Therefore, the cooling effect at the lower center of the reactor pressure vessel is better.
  • the housing is used as a heat dissipating fin that comes in contact with water injection, while the housing is located deep inside the reactor pressure vessel. Suitable for directing heat to the outside and cooling deep inside.
  • the injected water accumulates in the water storage area, reaches just below the center of the reactor pressure vessel, and reliably removes heat from the structure directly below. Water that has become hot due to the pressure, heat and cooling function in the water storage area escapes from the communication port and receives new water injection into the water storage area to obtain a continuous cooling effect.
  • a fourth invention is the reactor safety facility according to the third invention, wherein the water storage region is configured by using a heat insulating material covering the bottom of the reactor pressure vessel.
  • the water storage area can be constructed with the heat insulating material used for keeping the heat at the bottom of the reactor pressure vessel. The effect of minimizing the complexity of the configuration below the furnace pressure vessel is obtained.
  • the water injection port of the water injection equipment is constituted by a water spray nozzle, and the water spray nozzle is provided with a control rod drive mechanism housing and / or a control rod existing between the heat insulating material and the reactor pressure vessel.
  • a plurality of the core nuclear instrumentation housings are provided so as to surround the gathering region, and the direction of watering of the watering nozzle is directed to the control rod drive mechanism housing and the nuclear instrumentation housing. This is a reactor safety facility characterized by this.
  • a sixth invention is the reactor safety facility according to the fourth invention, wherein the communication port is provided with means for opening and closing the communication port.
  • the following operation and effect can be obtained in addition to the operation and effect of the fourth invention.
  • the communication holes are closed and the reactor pressure vessel is closed.
  • the thermal efficiency of the reactor can be increased by increasing the heat retention of the reactor. If the reactor pressure vessel needs to be cooled from the outside, the communication port is opened and the heat, pressure, and water in the water storage area are released from the communication port. After that, new water injection is continuously received in the water storage area, and the reactor pressure vessel is continuously cooled from the outside to ensure safety.
  • the means for opening and closing the communication port comprises: a heat retaining member that closes the communication port; and a communication rod based on the temperature of the control rod drive mechanism housing or the core instrumentation housing or the pressure in the water storage area.
  • Reactor safety equipment characterized by having a structure that removes the heat insulation member that blocks the mouth from the communication port.
  • the following operation and effect can be obtained in addition to the operation and effect of the sixth invention. That is, since the communication port is closed with a heat insulating material having a large heat insulating effect, heat leakage from the communication port is small, and the effect of further improving the thermal efficiency of the nuclear reactor can be obtained.
  • the insulation that closes the communication port can be removed based on the temperature of the reactor pressure vessel wall or the pressure in the water storage area, so that new water can be continuously received in the water storage area and the reactor pressure can be removed. Cool the container continuously from the outside to ensure safety.
  • An eighth invention is based on the third invention, and in the third invention, the water injection equipment is started to inject water based on a detection result of a temperature detector for detecting a temperature of a portion outside the reactor pressure vessel of the control rod drive mechanism housing or the in-core nuclear instrumentation housing.
  • Reactor safety equipment characterized by having control means.
  • the temperature of the part outside the reactor pressure vessel of the control rod drive mechanism housing or the core instrumentation housing is taken into account for the condition for starting water injection.
  • it is easy to accurately set the timing of the start of water injection.
  • the ninth invention is based on the eighth invention, wherein the detection result of the temperature detector and the water injection equipment Control means for starting water injection into the water injection equipment based on multiple pieces of information, including the results of the start operation from the start switch that prompts the start of operation and the detection result of the water level detector that detects the water level in the reactor pressure vessel.
  • This is a reactor safety facility characterized by the following features.
  • the timing of the start of water injection can be more accurately obtained.
  • the water storage region is formed of a heat insulating material covering a lower part of the reactor pressure vessel, and a communication port provided at a position higher than an inner bottom surface of the water storage region;
  • This is a reactor safety facility characterized by having a sprinkler nozzle as a water inlet.
  • water can be sprayed from the surroundings onto the control rod drive mechanism housing and the collecting area of the Z or the nuclear instrumentation housing to cool the housings efficiently.
  • the cooling effect is improved and safety is improved.
  • the eleventh invention is directed to a structure in which a heat insulating material at a lower portion of the reactor pressure vessel is also extended downward from the reactor pressure vessel to transfer heat inside the reactor pressure vessel to the outside,
  • a reactor safety facility comprising: a water storage area to be included; and a water injection facility to the water storage area.
  • the heat of the reactor pressure vessel is transferred to the water storage area by transferring the heat to the structure, and is cooled and cooled by water injection into the water storage area. Like this Thus, the heat that would damage the reactor pressure vessel is released to the outside and safety can be ensured.
  • the structure is a control rod drive mechanism housing and / or a nuclear instrumentation housing
  • the water storage area is constituted by a pedestal in a reactor containment vessel.
  • a water level detector is provided in the water storage area, and based on the detection result from the water level detector, the water injection equipment is adjusted so that at least a part of the control rod drive mechanism housing and the or the core instrumentation housing in the furnace is submerged.
  • a control means for controlling a water injection operation is provided, and the water injection equipment is provided with a plurality of water spray nozzles scattered around the control rod drive mechanism housing and / or the core instrumentation housing as a water injection port so as to surround the collective area.
  • Reactor safety equipment characterized in that the direction of water spray is directed to the control rod drive mechanism housing and / or the nuclear instrumentation housing in the reactor.
  • the control device controls the water injection water level so that the housing is always immersed in the water injection. In this way, effective and continuous cooling can be expected.
  • water is sprayed evenly from the surroundings to the control rod drive mechanism housing and / or the nuclear instrumentation housing in the reactor. Since the heat is supplied, the heat from the reactor pressure vessel that has conducted heat through the housing is taken away by the water spray, and a more effective cooling action is obtained.
  • FIG. 1 is a longitudinal sectional view of a lower part of a nuclear reactor according to a first embodiment of the present invention.
  • FIG. 2 is a diagram showing a starting logic of the water injection equipment according to the first embodiment of the present invention.
  • FIG. 3 is a graph showing a specification method according to the first embodiment of the present invention.
  • FIG. 4 is a graph showing the temperature of the housing and the passage of time according to the first embodiment of the present invention.
  • FIG. 5 is a longitudinal sectional view of a main part of a lower part of a nuclear reactor according to a second embodiment of the present invention.
  • FIG. 6 is a longitudinal sectional view of a lower part of a reactor according to a third embodiment of the present invention.
  • FIG. 7 is a longitudinal sectional view of a containment vessel according to a fourth embodiment of the present invention.
  • the basic configuration of the boiling water reactor (BWR) shown in Fig. 1 is as follows. That is, the reactor core 5 loaded with the fuel rods filled with nuclear fuel is stored in the reactor pressure vessel 1 in a state of being submerged by the coolant 4.
  • the reactor pressure vessel 1 is covered with a panel-shaped heat insulating material 6 to reduce heat loss due to heat radiation.
  • This heat insulator is composed of metal plates on the front and back, sandwiching components with poor heat conduction.
  • the hemispherical lower mirror part 2 of the reactor pressure vessel has a control rod drive mechanism housing containing a control rod drive mechanism that drives the control rods that control the output of the reactor core 5, and an in-core nuclear meter containing a measuring instrument.
  • the control rod drive mechanism housing and the in-core nuclear instrumentation housing are hereinafter referred to as unit housing 3.
  • Each of the housings 3 is a cylindrical structure, and is provided in the reactor pressure vessel 1 through the wall of the lower mirror section 2 of the reactor pressure vessel 1.
  • Nuclear power plants use nuclear reactors as follows. That is, the coolant 4 heated in the reactor core 5 in the reactor pressure vessel 1 boils to generate high-temperature and high-pressure steam.
  • the steam is driven to the turbine via piping connected to reactor pressure vessel 1. It is sent as a power source and used to drive the turbine.
  • the generator connected to the turbine also operates, generating power from the generator. The power is distributed to power consumers and used.
  • the reactor is emergency stopped, and the coolant of the coolant by the emergency core cooling system is used.
  • the core 5 is submerged by being injected into the pressure vessel 1 to cool the core 5.
  • Reactor pressure vessel 1 is housed in reactor containment vessel 9. Specifically, as shown in Fig. 7, it is mounted and stored on a cylindrical pedestal 10 built almost at the center of the primary containment vessel 9.
  • the lower mirror part 2 of the reactor pressure vessel 1 is surrounded by a heat insulating material 6 so as to reduce heat loss during normal operation.
  • the space 7 surrounded by the lower mirror 2 and the heat insulating material 6 is a water storage area, and the water storage area is formed by the heat insulating material 6 at the bottom and the horizontal periphery.
  • the heat insulating material 6 is supported by being attached to a common structure in a reactor containment vessel composed of a metal member such as an H-section steel.
  • the housing 3 passes through the bottom of the heat insulating material 6 and extends below the heat insulating material 6.
  • a communication port 15 is provided in the heat insulating material 6 that separates the bottom and the outside of the space 7 from each other.
  • the communication port 15 has a tubular pipe attached to the heat insulating material 6 to communicate inside and outside the space 7.
  • the opening of the communication port 15 on the space 7 side, that is, the upper opening is located higher than the lower end of the lower mirror 2 of the reactor pressure vessel 1.
  • a water injection system 11 is provided for the space 7 formed by the lower mirror 2 and the heat insulating material 6.
  • the water injection equipment 11 is connected to the annular water injection header pipe 16 arranged in the space 7 so as to surround the area R of the housing 3 group in the space 7 and the housing 3 group Placed so as to surround region R
  • the water spray nozzle 12 is directed in the water spray direction toward the housing 3.
  • the pump 13 of the water injection facility 11 starts, the pump 13 sucks cooling water from a water source (not shown) and pumps it to the pipe 17.
  • the cooling water is supplied from the pipe 17 to one pipe of the water injection header at a flow rate corresponding to the degree of opening, provided that the valve 14 is open, and finally, the cooling water is supplied from the watering nozzle 12. Is sprayed into the space 7 with water sprinkled, and cooling water is applied to the housing 3.
  • the control device 25 also has a signal 22 from a temperature detector 21 for detecting the surface temperature of the housing 3 and a signal from a water level detector 23 for detecting the water level in the reactor pressure vessel 1. 2 4 has been entered. Further, a monitoring device 28 and a manual switch 29 are connected to the control device 25.
  • the control logic of the control device 25 includes the start switch signal 301, the reactor water level low signal 302, the reactor housing temperature high signal 303, and the reactor housing temperature high signal 304. It consists of.
  • the reactor water level low signal 302 and the reactor housing temperature high signal 303 are generated, the signal 305a is generated.
  • the start switch signal 301 when the operator performs the start operation is generated, the water injection means start signal 310 is generated and the water injection means is started. .
  • the reactor housing temperature high and low signal 304 was generated along with the signal 300b, the water injection means start signal 310 was generated and the water injection equipment 11 Start 1 and read.
  • the set water level of the reactor water level low signal 302 be set sufficiently lower than the top of the available fuel of the fuel rods loaded in the reactor core 5.
  • the set temperature of the housing section high temperature signal 303 is lower than the set temperature of the housing section high temperature signal 304, and the temperature of the lower mirror section 2 during normal operation of the reactor (about 300 0 ° C).
  • the set temperature of the housing part high temperature signal 304 is lower than the damage limit temperature of the reactor pressure vessel 1 (approximately 1200 ° C) and sufficiently higher than the housing part high temperature signal 303. It is preferable to set to.
  • the monitoring device 28 shown in FIG. 1 enables the operator to monitor the temperature of the housing 3 based on the temperature signal from the temperature detector 21.
  • the heat dissipation when the cylindrical housing 3 is considered as a heat dissipation fin is defined by the following equation.
  • L is the height (m) of the upper opening of communication line 15 from the inner surface of the heat insulating material.
  • A An empty space consisting of the lower mirror part 2 of the reactor pressure vessel 1 and the heat insulator 6 Surface area (m 2 ) where housing 3 contacts cooling water between 7
  • the surface area A (L, H) where the cooling water injected into the space 7 from the housing 3 and the watering nozzle 12 contacts the space 7. Therefore, the surface area A (L, H) is defined by Equation 1 in order to obtain an arbitrary heat dissipation Qc (necessary heat removal).
  • the coolant 4 in the reactor pressure vessel 1 is lost,
  • the water level detector 23 generates a low reactor water level signal 302 and the high temperature core material dropped into the lower plenum 8 causes the lower mirror
  • the temperature of the section 2 and the housing 3 rises, and the temperature detector 21 generates a high temperature signal 303 of the reactor housing section.
  • the control device 2 By the operation of 5, the water injection equipment 11 is started to inject water into the space 7.
  • the temperature detector 21 generates a housing temperature high / low signal 304 due to a further rise in the temperature of the housing 3, and the water injection means 11 is automatically turned on. Operate. Thus, unnecessary activation of the water injection equipment 11 can be prevented, and the water injection equipment 11 can be reliably activated when necessary.
  • the pump 13 starts and the valve 14 opens, so that water injection from the watering nozzle 12 to the housing 3 starts.
  • the cooling water injected from the watering nozzles 12 is applied to the surface of the housing 3 to cool the surface, and falls to the bottom of the space 7 to be stored in the space 7. Since the housing 3 and the bottom of the lower mirror 2 are in contact with the cooling water stored in the space 7, the housing 3 and the bottom of the lower mirror 2 are cooled by the cooling water stored in the space 7.
  • water can be stored from the bottom of the space 7 to the height of the upper end of the communication port 15, as shown by the water storage level line shown by the two-dot chain line in Fig. 1.
  • Heat existing inside the reactor pressure vessel 1 is received and collected by the housing 3 located inside the reactor pressure vessel 1, and is transferred to the housing 3 located outside the reactor pressure vessel 1. . Outside its reactor pressure vessel 1
  • the heat transmitted to the housing 3 located in the space 7 is dissipated by the cooling water in the space 7 and taken away by the water cooling function.
  • the housing 3 since the housing 3 exhibits a fin effect for heat collection and heat dissipation, a large cooling effect in the reactor pressure vessel 1 can be expected. In this way, the heat in the deep part inside the reactor pressure vessel 1 is transferred to the housing 3 and radiated outside the reactor pressure vessel, and the deep inside part of the reactor pressure vessel 1 is actively cooled. be able to.
  • the cooling of the housing 3 by the cooling water stored in the space 7 is continued by the cooling water continuously injected from the watering nozzle 12.
  • the water stored in the space 7 starts flowing from the opening at the upper end of the communication port 15. It is discharged out of the space 7 through the inside of the communication port 15.
  • the space 7 absorbs heat from the housing 3 and the lower mirror portion 2 so that the cooling water in the space 7 evaporates and fills the space, and the space 7 tries to be in a state of high temperature and high pressure.
  • the steam, the pressure and the temperature are released to the outside of the space 7 through the communication port 15 in the same manner as the cooling water. Therefore, continuous cooling can be applied to the housing 3 and the lower mirror 2 by continuously injecting water into the space 7. In this way, the presence of the communication port 15 prevents the internal pressure of the space 7 from rising, so that the continuation of water injection is not hindered.
  • the height of the upper opening into the space 7 of the communication port 15 was set at a predetermined height set based on the amount of heat to be removed, so that water was released from the nozzles 12 Cooling water can be stored in the space 7 to remove the amount of heat specified by the equation (1). Furthermore, since the height of the upper opening of the communication port 15 is set to be equal to or higher than the lower end of the lower mirror part 2, the lower mirror part 2 can be cooled by immersing it in the cooling water stored in the space 7, and if only the housing 3 is used. In addition, it is possible to promote the suppression of the temperature rise of the lower mirror section 2. In this way, the housing 3 is effectively cooled by the injection of the cooling water as shown in FIG. 3 and the temperature rise of the lower mirror 2 is suppressed, so that the pressure of the reactor pressure vessel 1 is reduced. Damage can be prevented.
  • a heat insulating material 32 is installed inside the lower opening of the communication port 15 provided in the heat insulating material 6 so as to close the opening.
  • the heat insulating material 32 is attached to the support 33, and the support 33 is joined to the lower mirror 2 at the contact portion 31 made of a material having a low melting point.
  • the melting point temperature of the material of the contact part 31 is lower than the failure limit temperature of the reactor pressure vessel 1 (about 1200 ° C), and the temperature of the lower mirror part 2 during normal operation of the reactor (about 300 ° C). It is preferable that the temperature is sufficiently high.
  • Other configurations are the same as those of the first embodiment shown in FIG.
  • the contact part 31 melts.
  • the lower part of the mirror is moved away from the lower mirror part by two, and the heat insulator 32 falls down from the inside of the communication port 15 with the support 33 to open the communication port 15 closed with the heat insulator 32. it can.
  • the communication port 15 is opened, the configuration is the same as that of the first embodiment described, and continuous cooling can be performed by continuous water injection into the space 7. Other operations are the same as in the first embodiment described.
  • the heat loss of the reactor pressure vessel during normal operation prevents heat leakage from the communication port 15 by closing the communication port 15 with the heat insulating material 32. , Are suppressed. Therefore, the heat loss of the reactor pressure vessel during normal operation can be smaller than in the first embodiment.
  • a lid 34 made of a heat insulating material is installed inside the lower opening of the communication port 15.
  • Other configurations are the same as those of the first embodiment shown in FIG.
  • the lid 34 is provided when the head pressure is applied when a water level is formed on the lid 34 from the bottom of the space 7 of the communication port 15 to the height of the upper opening of the communication port 15.
  • the installation strength is set so that 3 and 4 will be removed.
  • the heat loss of the reactor pressure vessel during normal operation prevents the heat leakage from the communication port 15 because the communication port 15 is closed by the lid 34. Is suppressed. Therefore, the heat loss of the reactor pressure vessel during normal operation can be smaller than in the first embodiment.
  • a water injection header pipe 16 of the water injection equipment 11 is installed below the heat insulating material 6.
  • a control device 203 for outputting a control signal 204 for controlling the valve 14 of the water facility 11 is provided.
  • Other configurations are the same as those of the first embodiment shown in FIG.
  • the direction of water injection from watering nozzles 12 should be directed to nozzle 3.
  • the position of the water spray nozzle 12 is as high as possible than the heat insulating material 6 in order to increase the contact area of the cooling water discharged from the nozzle 3 and the water spray nozzle 12. It is preferable to be installed in
  • the controller 203 adjusts the opening of the valve 14 when the water level in the reactor containment vessel 8 exceeds a predetermined level. To do so.
  • the amount of heat radiation when the cylindrical housing 3 is considered as a heat radiation fin is defined by the following equation.
  • Equation 2 Temperature difference between the cooling water and the surface of the housing 3 (K) In order to improve this heat dissipation, it is necessary to increase the surface area A (L w) where the housing 3 contacts the cooling water. Therefore, the surface area A (L w) is defined by Equation 2 in order to obtain an arbitrary heat dissipation Q c.
  • Equation 2 A (L w) ⁇ Q c / (h 0 0)... Equation 2
  • Q c is the required heat removal (W) If the shape and number of the housing 3 of the reactor pressure vessel 1 are determined, the required heat removal amount Qc can be obtained by setting the height Lw of the set water level from the lower end of the housing 3 so as to satisfy Equation 2. Can be secured.
  • the water injection facility 11 starts water injection similarly to the first embodiment. Due to the water injection, cooling water is discharged from the spray nozzle 12 to the surface of the housing 3, and the water level in the pedestal 10 rises.
  • the water level detector 201 detects the set water level and outputs the water level detector 201 to the control device 203. Send a signal.
  • the control device 203 receiving the output signal of the water level detector 201 outputs a control signal 204 for decreasing the opening of the valve 14 to the drive device of the valve 14 and throttles the valve 14. To reduce the amount of water injected.
  • the control device 203 sends a control signal to the drive device of the valve 14 to fully close the valve 14. Is output to stop water injection by the water injection equipment 11 and the housing is cooled by the cooling water stored in the pedestal 10.
  • the control device 203 transmits the valve 14 Outputs a control signal to increase the valve opening, increases the water injection by the water injection equipment 11, and raises the level of the cooling water stored in the pedestal 10 from the lower end of the housing 3 to the set water level L w.
  • the water injected from the water injection equipment 11 is stored in the pedestal 10 to promote cooling of the housing part, and furthermore, it is possible to suppress a rise in the temperature of the lower mirror part 2. This can prevent the reactor pressure vessel 1 from being damaged. Also note that the water level detector 201 only ensures the required heat removal. Since the amount of water can be limited, unnecessary injection of water into the reactor containment vessel 9 is restricted, and the reduction of the free space volume inside the reactor containment vessel 9 due to an increase in cooling water is suppressed. Can be.
  • the end of the pipe 17 of the stop and water injection equipment 11 may be opened to the inside of the space 7 or the pedestal 10 so as to face it.
  • the controller 25 automatically controls the reactor pressure. Cooling water for cooling the outer surface of the housing 3 that penetrates the lower part of the container 1 is started, and the housing 3 is made to function as a water-cooled fin. The temperature rise in the reactor section and the temperature rise in the bottom of the reactor pressure vessel 1 are suppressed. For this reason, even if an accident occurs that the core 5 melts and the core melt falls to the bottom of the reactor pressure vessel 1, damage to the reactor pressure vessel can be prevented.
  • the reactor safety equipment according to the present invention is useful as a safety equipment applied to a nuclear power plant nuclear reactor or a power reactor.

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  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

La présente invention concerne un équipement de sécurité pour réacteur, permettant de lutter contre un accident de fusion du coeur et comprenant un équipement de remplissage d'eau (11) qui déverse de l'eau dans des parties de boîtier (3) d'une enceinte sous pression du réacteur (1), à l'intérieur d'un espace (7) formé d'une plaque terminale inférieure (2) et d'un matériau d'isolation (6). Un signal (22), issu d'un détecteur de température (21) qui détecte la température superficielle des parties de boîtier (3), et un signal (24), issu d'un détecteur de niveau d'eau (23) qui détecte un niveau d'eau dans l'enceinte sous pression du réacteur (1), sont entrés dans un dispositif de commande (25) et, lorsque la température des parties de boîtier (3) excède une température spécifiée, des signaux de mise en marche (27, 28) sont transmis à une pompe (13) et à une soupape (14) de l'équipement de remplissage d'eau (11), de façon à déverser de l'eau de refroidissement, à partir d'une buse de pulvérisation (12), dans les parties de boîtier (3). Etant donné qu'une pression et de l'eau chauffée, issues de l'intérieur de l'espace (7), sont évacuées à travers un port de communication (15) à l'extérieur de l'espace (7), l'enceinte sous pression du réacteur (1) est continuellement refroidie jusqu'à un état sûr à travers les parties de boîtier (3).
PCT/JP1999/004639 1999-08-27 1999-08-27 Equipement de securite pour reacteur WO2001016962A1 (fr)

Priority Applications (1)

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PCT/JP1999/004639 WO2001016962A1 (fr) 1999-08-27 1999-08-27 Equipement de securite pour reacteur

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
PCT/JP1999/004639 WO2001016962A1 (fr) 1999-08-27 1999-08-27 Equipement de securite pour reacteur

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WO2001016962A1 true WO2001016962A1 (fr) 2001-03-08

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Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2015040732A (ja) * 2013-08-21 2015-03-02 株式会社東芝 原子炉圧力容器及び原子炉圧力容器の冷却方法
JP2015087387A (ja) * 2013-09-27 2015-05-07 長浦　善昭 福島第一原子力発電所を中心として建設をする凍土壁を凍結する冷媒として、膨大な冷熱を安価にて供給をすることが出来る、−１６２℃の液化ｌｎｇの気化熱を使用して凍土壁を凍結する方法。
CN105788670A (zh) * 2016-06-01 2016-07-20 中国核动力研究设计院 一种堆芯补水箱模拟体的改进结构
JP2017090401A (ja) * 2015-11-17 2017-05-25 日立Ｇｅニュークリア・エナジー株式会社 原子炉水位推定装置
CN114068052A (zh) * 2021-11-30 2022-02-18 中国核动力研究设计院 一种压水堆堆腔温度监测系统

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0875887A (ja) * 1994-09-05 1996-03-22 Mitsubishi Atom Power Ind Inc 原子炉の炉心デブリ冷却装置
JPH09119995A (ja) * 1995-10-26 1997-05-06 Hitachi Ltd 原子炉プラント
JPH10300883A (ja) * 1997-04-30 1998-11-13 Toshiba Corp 原子炉容器の冷却装置及び冷却方法

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0875887A (ja) * 1994-09-05 1996-03-22 Mitsubishi Atom Power Ind Inc 原子炉の炉心デブリ冷却装置
JPH09119995A (ja) * 1995-10-26 1997-05-06 Hitachi Ltd 原子炉プラント
JPH10300883A (ja) * 1997-04-30 1998-11-13 Toshiba Corp 原子炉容器の冷却装置及び冷却方法

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2015040732A (ja) * 2013-08-21 2015-03-02 株式会社東芝 原子炉圧力容器及び原子炉圧力容器の冷却方法
JP2015087387A (ja) * 2013-09-27 2015-05-07 長浦　善昭 福島第一原子力発電所を中心として建設をする凍土壁を凍結する冷媒として、膨大な冷熱を安価にて供給をすることが出来る、−１６２℃の液化ｌｎｇの気化熱を使用して凍土壁を凍結する方法。
JP2017090401A (ja) * 2015-11-17 2017-05-25 日立Ｇｅニュークリア・エナジー株式会社 原子炉水位推定装置
CN105788670A (zh) * 2016-06-01 2016-07-20 中国核动力研究设计院 一种堆芯补水箱模拟体的改进结构
CN114068052A (zh) * 2021-11-30 2022-02-18 中国核动力研究设计院 一种压水堆堆腔温度监测系统

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